Electrical power generation apparatus and method

Abstract

A mobile fusion device (MFD) comprises three main sections: the MFD reactor (467), MFD support sub-systems (468), and the MFD support and fuel injection sub-systems (469), which are indicated by broken lines in Figure 1 The MFD reactor (467) is where the Deuterium and Tritium fuel is heated to high enough temperatures and densities and confinement times that fusion occurs, releasing neutrons that are absorbed in and heats up the 17Li-83Pb breeder blanket where more Tritium fuel is bred and where heat is transferred to Helium coolant. The MFD support sub-systems (468) houses auxiliary power units that generate electricity to power the electrical sub-systems of the MFD, and houses the MFD control computer, and where the Helium coolant is cryogenically cooled and purified, and where the 17Li-83Pb breeder blanket fluid is purified by separating and storing Deuterium fuel and Tritium fuel and Helium coolant, and where a Helium heat exchanger is located. The MFD support and fuel injection sub-systems (469) houses Deuterium and Tritium neutral beam injection plasma heating systems and a Deuterium and Tritium fuel gas puffer system and a Deuterium and Tritium fuel storage and pellet manufacturing system, and where the 17Li-83Pb breeder blanket fluid is purified by separating and storing Deuterium fuel and Tritium fuel and Helium coolant, and where a Helium heat exchanger is located, and where the Helium coolant is cryogenically cooled and purified, and houses auxiliary power units that generate electricity to power the electrical sub-systems of the MFD. The MFD is housed within a multi-layered pressurised outer containment pod MLP, which has a multi-layered pressurised rear access hatch MLH. The MFD is mounted on a sliding raft SR for ease of access.

Description

[0001] Electrical Power Generation Apparatus and Method

[0002] This invention relates to an electrical power generation apparatus and method, and more particularly to a fusion apparatus and method, and is concerned particularly, although not exclusively with a mobile apparatus that could be fitted to a diverse range of manned or unmanned sub-sea, sea, land, aerial , space-based platforms and power stations , and with a method of operating the same .

[0003] Since 1958 when the first "closed" Tokamaks fusion devices were developed, Tokamaks and Spherical Tokamak fusion devices have won over "open mirror" fusion devices due to their higher energy confinement time physics abilities and for political reasons . However, in recent decades , well confined "closed" Tokamaks and Spherical Tokamak fusion devices have had to be "opened up" for plasma fuelling and plasma puri fication and maintenance reasons to try to turn them into practical electricity generating fusion powerplants .

[0004] However, plasma fuelling, and plasma puri fication and maintenance are more easily achieved in "open mirror" fusion devices due to their inherent open mirror design configuration . The development path of "open mirror" fusion devices over the past six decades has unfortunately been under-developed, even though "open mirror" fusion devices easily solved engineering issues such as plasma fuelling and plasma puri fication and maintenance which were not at the top of the then-list of priority engineering and physics design requirements when more research was focussed on developing high energy confinement "closed" Tokamaks and Spherical Tokamak fusion devices .

[0005] It would therefore be highly beneficial i f the lagging performance of "open mirror" fusion devices compared to "closed" Tokamaks and Spherical Tokamak fusion devices could be corrected by designing an innovative and highly integrated "open mirror" fusion device that could have all of the required integrated sub-systems to achieve electricity generating power station performance .

[0006] Embodiments of the present invention aim to correct the deficiencies of existing "closed" Tokamaks and Spherical Tokamak fusion devices and exi sting "open mirror" fusion devices , and to provide a mobile fusion device, hereinafter "MFD" that is designed to be linear and scalable and be small enough to be fitted as the fusion powerplant of diverse manned or unmanned sub-sea, sea, land, aerial , space-based platforms . The complex concave curvature magnetic field structure within existing "closed" Tokamaks and Spherical Tokamak fusion devices minimi zes their Beta B, which is the ratio of thermal plasma pressure to the magnetic field pressure , and creates magnetohydrodynamic MHD instabilities . Embodiments of the present invention aim to provide a more practical MFD design that has inherent design flexibility due to its innovative linear design configuration and its sub-systems modularity, that should allow it to be scaled to suit the power needs of consumers and platforms , and its very di f ferent convex internal magnetic field structure should maximi ze its achievable Beta B and maximi ze its steady state MHD stability .

[0007] The present invention is def ined in the accompanying independent claims , to which reference should now be made . Further, preferred features are to be found in the sub-claims appended thereto .

[0008] According to one aspect of the present invention, there is provided a mobile fusion device , comprising a fusion reactor for fusing atomic nuclei in a plasma of Deuterium and Tritium, a controllable magnetic confinement system for confining the plasma within the reactor, and a plasma heating system for heating the plasma, wherein the plasma heating system is arranged to heat the plasma by a plurality of methods including alpha channelling ef fect heating, in which Helium nuclei created in the plasma by the fusion of Deuterium and Tritium trans fer as much of their energy to the plasma before being removed from the plasma .

[0009] In another aspect , the present invention provides a mobile fusion device , comprising a fusion reactor for fusing atomic nuclei in a plasma of Deuterium and Tritium, a controllable magnetic confinement system for confining the plasma within the reactor, a breeder blanket at least partly surrounding the reactor and arranged to breed Tritium from free neutrons created by the fusion of the Deuterium and the Tritium, and a Helium recycling system arranged to recycle Helium created in the fusion reaction for use in a liquid Helium cooling system .

[0010] According to another aspect of the present invention, there is provided a mobile fusion device comprising a fusion reactor and support systems , wherein the device comprises a containment pod arranged to house the reactor and the support systems that are slidably mounted in the pod, and wherein the pod has an openable pod hatch .

[0011] According to a further aspect of the present invention, there is provided a mobile fusion device comprising a fusion reactor and support systems mounted in a pod, wherein the pod is mountable on or in a moveable vessel and is aerodynamically shaped .

[0012] In one aspect of the present invention, a or the mobile fusion device (MFD) comprises one or more of the following : • A multi-layered pressuri zed outer containment pod has a multi-layered pressuri zed outer containment pod rear access hatch;

[0013] • Two separated and fully integrated and electrically powered Deuterium and Tritium direct internal recycling systems ;

[0014] • Two separated and fully integrated and electrically powered Deuterium and Tritium inner fuel cycle systems ;

[0015] • Two separated and fully integrated and electrically powered Deuterium and Tritium outer fuel cycle systems ;

[0016] • Seven fully integrated and electrically powered plasma heating methods ;

[0017] • External moveable actively cooled electromagnetic field coils and a very large external moveable pressurised Helium cooled superconducting electromagnetic field coil and two large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coils that collectively magnetically confine the plasma within the MFD reactor ;

[0018] • The magnetically confined plasma is magnetically diverted into a fully integrated Helium cooled primary divertor and a fully integrated Helium cooled secondary divertor that are located at either end of the MFD reactor ;

[0019] • The space between the MFD reactor outer casing and the MFD reactor inner vacuum chamber has a plurality of LMLi- Pb Tritium breeding blanket layers that have a plurality of concentric layers of pressuri zed Helium cooling tubes ; • Two separated fully integrated heated Helium compact heat exchangers ;

[0020] Four separated fully integrated auxiliary power units ;

[0021] • Sensors supply information to the control computer that controls the operation of the integrated sub-systems of the MFD .

[0022] A multi-layered pressuri zed outer containment pod may have a multi-layered pressuri zed outer containment pod rear access hatch, that can be opened and closed that collectively house internally the slideable MFD reactor and the slideable MFD support sub-systems and the slideable MFD support and fuel inj ection sub-systems , which minimi zes its aerodynamic drag coef ficient , and maximi zes its ballistic protection and survivability, and minimi zes its acoustic noise signature emissions , and minimi zes the ris k of Tritium egress to the outside environment .

[0023] There may be provided two separate direct internal recycling systems with one located in the MFD support sub-systems and another in the MFD support and fuel inj ection sub-systems , comprising two separate vacuum pumping systems that each have a metal foil pump MFD that is connected on one side to a linear di f fusion pump and to a liquid ring pump, and on another side to a second linear di f fusion pump and to a second liquid ring pump, and the primary vacuum pumping linear di f fusion pumps in series with the rough pumping liquid ring pumps , will collectively allow the vacuum pumping of the MFD reactor inner vacuum vessel and gas separation of Helium, Deuterium, Tritium and other impurities required for the operation of the MFD, and pure Deuterium and Tritium fuel is trans ferred by pipework to the two liquid ring pump main chambers and is then trans ferred to the two liquid ring pump gas coolers and is then trans ferred into the Deuterium and Tritium fuel gas puf fer system and the Deuterium and Tritium fuel is then inj ected back into the MFD reactor .

[0024] Two separate inner fuel cycle systems may comprise a first inner fuel cycle system that involves Argon, Helium, Deuterium and Tritium and other impurities that are pumped out through the primary divertor vacuum chamber pumping channels and out through the primary divertor Helium cooled transparent liner pumping plate and out through the primary divertor vacuum chamber pumping pipe that is connected to the first MFD inlet located in the MFD support sub-systems of the MFD, and a second inner fuel cycle involves Argon, Helium, Deuterium and Tritium and other impurities that are pumped out through the secondary divertor vacuum chamber pumping channels and out through the secondary divertor Helium cooled transparent liner pumping plate and out through the secondary divertor vacuum chamber pumping pipe that is connected to the second MFD inlet located in the MFD support and fuel inj ection sub-systems of the MFD, and Hydrogen gas and Hydrogen isotopes , Helium and other impurities are then trans ferred by pipework to the two liquid ring pump main chambers and then to the two liquid ring pump gas coolers , and the two liquid ring pump gas coolers are used to cool the Hydrogen gas and Hydrogen isotopes , Helium and other impurities that are trans ferred by pipework into the two separate TCFRC isotope separators that can separate Tritium to the two Tritium storage systems and is then trans ferred by pipework to the two TRC Tritium storage systems of the outer fuel cycle systems and is then trans ferred to the Tritium neutral beam inj ection heating systems which fire Tritium neutral particles into the MFD reactor, and the Tritium can also be inj ected back into the MFD reactor as millimeter-si zed frozen Tritium pellets that are fired at thousands of km / h from the Deuterium and Tritium fuel storage and pellet manufacturing inj ection tube , and Deuterium separated by the two TCFRC isotope separators will be trans ferred by pipework to the two Deuterium storage systems and the separated Deuterium can then be inj ected back into the MFD reactor as millimeter-si zed frozen Deuterium pellets that are fired at thousands of km / h from the Deuterium and Tritium fuel storage and pellet manufacturing inj ection tube or can be inj ected back into the MFD reactor as Deuterium neutral particles using the Deuterium neutral beam inj ection heater, and impurities separated will be trans ferred by pipework to the two impurities storage systems , and Helium separated will be trans ferred by pipework to the two main Helium storage systems and is then trans ferred by pipework to the two Helium cryogenic cooling systems .

[0025] Two separate outer fuel cycle systems with one located in the MFD support sub- systems and another in the MFD support and fuel inj ection sub-systems , may involve Helium bubbles being generated in the low pressure loop by desorption in the two 17Li- 83Pb Helium separators and where Helium gas containing Tritium gas is trans ferred by pipework to the two Helium Tritium separators and where the removal of Tritium from Helium can be accomplished by selective absorption at room or cryogenic temperatures onto molecular sieve beds , and 17Li- 83Pb with Tritium and other impurities in it is then trans ferred from the two 17Li- 83Pb Helium separators and into two separate 17Li- 83Pb Tritium recovery systems which each have a Vanadium high permeable membrane that has a high permeability of Tritium that has been produced by the neutrons that are generated by the fusion of Deuterium and Tritium bombarding the breeder blanket pure LMLi-Pb to create more Tritium, that is then passed into two separated three stacked Yttrium solid getter beds which have a very high af finity for Hydrogen isotopes such as Tritium and which are designed as a practical pair of Tritium recovery systems , with the two separated three stacked Yttrium solid getter beds being used alternately in three modes which are operational mode , regenerative mode and standby mode , and the separated Tritium can then be inj ected back into the MFD reactor as millimetersi zed frozen Tritium pellets that are fired at thousands of km / h from the Deuterium and Tritium fuel storage and pellet manufacturing inj ection tube or can be inj ected back into the MFD reactor as Tritium neutral particles using the Tritium neutral beam inj ection heater .

[0026] In a preferred arrangement , seven fully integrated and electrically powered plasma heating methods are used by the MFD : ion cyclotron resonance heating, electron cyclotron resonance heating, Deuterium neutral beam inj ection heating, Tritium neutral beam inj ection heating and magnetic field variation plasma compression heating using magnetic field variation through the variation of current in the primary divertor end external moveable actively cooled sweeping electromagnetic field coil , the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil , the small external moveable actively cooled electromagnetic field coils , the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil , the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil , the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coils , and the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil , and magnetic field variation plasma compression heating using the physical longitudinal movement of the primary divertor end external moveable actively cooled sweeping electromagnetic field coil , the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil , the small external moveable actively cooled electromagnetic field coils , the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil , the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil , the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil , and hot-ion mode alpha channelling ef fect heating using the ion cyclotron resonance heating systems .

[0027] The plasma may be magnetically confined within the MFD reactor with the primary divertor end external moveable actively cooled sweeping electromagnetic field coil , the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil , the small external moveable actively cooled electromagnetic field coils , the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil , the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil , the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil that can all be moved longitudinally about the MFD reactor outer casing with linear actuators , apart from the two large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coils , that are all controlled by the MFD control computer .

[0028] The primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil and the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil may both be designed to create magnetic mirror points that are designed to reflect plasma within the MFD reactor and decrease the axial point cusp plasma losses along the central longitudinal axis of the MFD reactor, so minimising the amount of fusion plasma that can escape from either end of the MFD reactor, so maximi zing energy confinement time , and the two magnetic mirror points will not operate perfectly and some plasma will not be reflected by the magnetic mirror points which are the axial point cusp plasma losses which are magnetically confined and diverted into a primary divertor and a secondary divertor located at either end of the MFD reactor , respectively, and are magnetically swept onto Helium cooled Tungsten energy dump targets using the primary divertor end external moveable actively cooled sweeping electromagnetic field coil and the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil , respectively, and are reduced in flux intensity by neutral gas that is pumped into the primary divertor and the secondary divertor .

[0029] The space between the MFD reactor outer casing and the MFD reactor inner vacuum chamber may include four LMLi-Pb Tritium breeding blanket layers that are separated by three concentric layers of Helium cooling tubes and the breeder blanket pure LMLi-Pb may be used to breed Tritium fuel and pumped around the MFD using the breeder blanket LMLi-Pb pumps .

[0030] The MFD reactor that is interconnected to MFD support subsystems and to MFD support and fuel inj ection sub-systems may be all cooled with Helium coolant that is cooled by two Helium heat exchangers , one of the Helium heat exchangers being located within the MFD support sub-systems and the other Helium heat exchanger being located within the MFD support and fuel inj ection sub-systems , and where heated Helium coolant that has had Tritium and other impurities removed by the two Helium Tritium separators located within the two outer fuel cycles of the MFD is trans ferred by pipework into the two Helium heat exchanger hot-to-cold pipework, and as the heated Helium coolant travels along and through the two Helium heat exchanger hot-to-cold pipework, the heat energy from the heated Helium coolant is trans ferred to the cooled Helium coolant that is pumped from outside of the MFD that travels in the opposite direction along and through the two Helium heat exchanger cold-to-hot pipework, and the cooled Helium coolant is then pumped out of the two Helium heat exchanger hot-to- cold pipework and is used to cool the MFD, and the heated Helium coolant is then pumped out of the two Helium heat exchanger cold-to-hot pipework and can be used to heat an external Helium and steam heat exchanger used by a land-based MFD electricity generating power station, or can be used to heat an external Helium and steam heat exchanger used by a large container carrying ship, or can be used to heat an external Helium and steam heat exchanger used by a submarine , or can be used within Helium heat exchanger high by-pass turbofan engines used by a large aircraft , or can be used within Helium closed Brayton cycle ( CBC ) electrical power units used by spacecraft .

[0031] The convoluted compact magnetic bottle with magnetic mirror ends magnetic field line topography within the MFD reactor may be created by the primary divertor end external moveable actively cooled sweeping electromagnetic field coil , the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil , the small external moveable actively cooled electromagnetic field coils , the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil , the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil , the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil , the two large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coils that are collectively designed to maintain the strongest possible magnetically confined plasma boundary wall that consists of a scrape-of f magnetically confined plasma layer that magnetically confines the fusion plasma and prevents the fusion plasma from expanding within the MFD reactor .

[0032] Preferably, the magnetic field topography within the MFD reactor of the MFD is a convoluted compact magnetic bottle with magnetic mirror ends magnetic field lines which features axial point cusp magnetic field lines and radial ring cusp magnetic field lines whose magnetic field strength increases with radial distance from the central longitudinal axis of the MFD reactor of the MFD, and the externally applied magnetic field lines are inward directed and have a pos itive outward gradient and are convex shaped which strengthen with radial distance and so are able to counteract increasing plasma pressure with its radially strengthening magnetic field pressure which should confer very high magnetohydrodynamic stabili zation and B« l , so that as the plasma pressure from fusion reactions within the MFD reactor increases and the fusion plasma attempts to expand, the internal magnetic field configuration of the MFD becomes stronger at the magnetically confined plasma boundary wall , so counteracting and pushing back on the fusion plasma within the MFD reactor and so increasing the magnetic field confinement of the fusion plasma within the MFD reactor, which unlike a Tokamak fusion reactor such as ITER ®, gives the MFD reactor within the MFD an inbuilt sel f-regulating magnetic field plasma confinement feedback design feature .

[0033] In a preferred arrangement , the MFD design should have smaller plasma ion and plasma electron energy and particle losses than existing Tokamak fusion reactor designs such as ITER ®, as plasma can detach and exit the ITER ® Tokamak fusion reactor design at many more locations than the more compact MFD reactor of the MFD design, as the creation of an internal magnetic field configuration of the convoluted compact magnetic bottle with magnetic mirror ends magnetic field line topography within the MFD reactor should ensure that the li fetime of plasma ions and plasma electrons wil l be increased inside the MFD reactor of the MFD, which should increase the energy confinement time and should increase the ability of the MFD reactor of the MFD to produce more fusion power with the minimum amount of electrical power required initially to heat the plasma by the seven plasma heating methods used by the MFD .

[0034] Deuterium and Tritium gas fuel may be inj ected into the MFD reactor, and when high velocity Deuterium neutral particles are fired from the Deuterium neutral beam inj ection heater and when high velocity Tritium neutral particles are fired from the Tritium neutral beam inj ection heater that will have traj ectory paths that converge on the centre of the central plasma region, and when the Deuterium and Tritium fuel storage and pellet manufacturing container gas gun is used to propel millimeter-si zed frozen Deuterium pellets and millimeter-si zed frozen Tritium pellets into the fusion plasma that will have traj ectory paths that converge on the centre of the central plasma region, and an increase in the electrical power to the electron cyclotron resonance heaters and to the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil and to the two large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coils , will collectively prevent the expansion and will actually compress and will heat up and will reduce the volume of the central plasma region until the plasma density and plasma temperature and energy confinement time within the central plasma region are high enough for fusion reactions to occur, which will result in the creation of the magnetically compressed central fusion plasma volume , and the plasma pressure will increase which wil l result in the magnetically compressed central fusion plasma volume to inflate and occupy an increasing volume of the space between the two large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coils and the MFD reactor inner vacuum chamber, which will increase the fusion reaction power output from the MFD reactor .

[0035] Preferably, an increase in the electrical power to the ion cyclotron resonance heaters and to the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil and to the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil and to the three adj acent small external moveable actively cooled electromagnetic field coils , will collectively prevent the expansion and will actually compress and will heat up and will reduce the volume of the left central plasma region until the plasma density and plasma temperature and energy confinement time within the left central plasma region are high enough for fusion reactions to occur, which will result in the creation of the magnetically compressed primary divertor end fusion plasma volume , and the plasma pressure will increase which will result in the magnetically compressed primary divertor end fusion plasma volume to inflate and occupy an increasing volume of the space between the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil and the MFD reactor inner vacuum chamber which will increase the fusion reaction power output from the MFD reactor .

[0036] Preferably, an increase in the electrical power to the ion cyclotron resonance heaters and to the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil and to the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil and to the three adj acent small external moveable actively cooled electromagnetic field coils , will collectively prevent the expansion and will actually compress and will heat up and will reduce the volume of the right central plasma region until the plasma density and plasma temperature and energy confinement time within the right central plasma region are high enough for fusion reactions to occur, which will result in the creation of the magnetically compressed secondary divertor end fusion plasma volume , and the plasma pressure will increase which will result in the magnetically compressed secondary divertor end fusion plasma volume to inflate and occupy an increasing volume of the space between the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil and the MFD reactor inner vacuum chamber which will increase the fusion reaction power output from the MFD reactor .

[0037] The sub-systems within the MFD may be powered initially by four separated fully integrated heated Helium auxiliary power units that use heated Helium coolant from the two separated fully integrated heated Helium compact heat exchangers or external power sources , and where the MFD reactor sub-systems and the interconnected MFD support sub-systems and the MFD support and fuel inj ection sub-systems and the plasma conditions within the MFD reactor of the MFD need to be continuously measured by sensors and which are used by the MFD control computer to control and optimise the performance of the MFD .

[0038] The MFD could be used to heat Helium coolant that could be used to heat an external Helium and steam heat exchanger to produce steam that could be used to rotate a steam turbine and electrical generator within land-based or sea-based MFD electricity generating power stations .

[0039] The MFD could be used to heat Helium coolant that could be used to heat an external Helium and steam heat exchanger to produce steam that could be used to rotate a steam turbine and electrical generator within MFD powered ship or submarine manned or unmanned platforms .

[0040] The MFD could be used to heat Helium coolant that could be used within either a plurality of Helium heat exchanger high by-pass turbofan engines to propel large aerial manned or unmanned platforms , or wherein a MFD could be used to heat Helium coolant that could be used within a plurality of Helium closed Brayton cycle ( CBC ) electrical power units that could be used to power a plurality o f directable laser propulsors and whereby Helium produced as a fusion process byproduct could also be used by manoeuvring space thrusters that could collectively propel and manoeuvre interstellar spacecraft manned or unmanned platforms .

[0041] The invention may include any combination of the features or limitations referred to herein, except such a combination of features as are mutually exclusive , or mutually inconsistent .

[0042] Applications of the MFD that utili ze a MFD reactor that is interconnected to MFD support sub-systems and to MFD support and fuel inj ection sub-systems , include a MFD that can heat Helium coolant that is then pumped out of the two Helium heat exchangers cold-to-hot pipework and can be used to heat an external Helium and steam heat exchanger used by a land-based MFD electricity generating power station, or can be used to heat an external Helium and steam heat exchanger used by a large commercial ship or warship that is fitted with a MFD, or can be used to heat an external Helium and steam heat exchanger in a submarine , or can be used to heat Helium and heated air heat exchanger high by-pass turbofan engines that can propel large aircraft , or can be used to generate electricity to power spacecraft laser propulsors that can propel spacecraft , or can be installed on sub-sea, sea, land, aerial , space-based manned or unmanned platforms .

[0043] In a first embodiment , a MFD is installed in a land-based or sea-based MFD electricity generating power station . It would be environmentally and economically beneficial i f large electricity generating power stations in the future could stop producing greenhouse gases from the combustion of fossil fuels and could stop using fission nuclear reactors that produce very long lasting and very radioactive waste products , and instead be powered by one or more MFDs that could heat Helium coolant that could then be used by multiple Helium and steam heat exchangers to produce steam which could then be used to drive a steam turbine that rotates an electrical generator .

[0044] In a second embodiment , a MFD is installed in a large commercial ship or warship . It would be environmentally and economically beneficial i f large commercial ships and warships in the future could stop producing greenhouse gases from the combustion of fossil fuels and emit less noise and instead be powered by one or more MFDs that could heat Helium coolant that could then be used by multiple Helium and steam heat exchangers to produce steam which could then be used to drive a steam turbine that rotates a steam turbine shaft and gearbox that rotates a propeller to propel the large commercial ship or warship across the sea surface .

[0045] In a third embodiment , a MFD is installed in a submarine . It would be environmentally and economically beneficial i f submarines in the future could dispense with combusting fossil fuels , fuel cells and pressurised water fission reactors and instead were powered by a scaleable , non-polluting, low acoustic signature , one or more MFDs that could heat Helium coolant that could then be used by multiple Helium and steam heat exchangers to produce steam which could be used to drive a steam turbine that rotates a steam turbine shaft and gearbox that rotates a pumpj et propulsor which propels the submarine under the sea surface .

[0046] In a fourth embodiment , a MFD and Helium and heated air heat exchanger high by-pass turbofan engines are installed on aerial platforms like airliners . It would be environmentally and economically beneficial i f large aircraft in the future could stop producing greenhouse gases from the combustion of fossil fuels and instead be powered by one or more MFDs that could heat Helium coolant that could then be used by multiple Helium and heated air heat exchanger high by-pass turbofan engines that provide the large aircraft zero emissions thrust .

[0047] In a fi fth embodiment , the MFD spacecraft propulsion system could be used as an interstellar propulsion system and could utili ze heated Helium closed Brayton cycle ( CBC ) electrical power units that could be used to power a plurality of directable laser propulsors , and Helium produced as a fusion process byproduct could be used by manoeuvring space thrusters to propel interstellar spacecraft manned or unmanned platforms .

[0048] Preferred embodiments of the present invention will now be described, by way of example only, with reference to the accompanying diagrammatic drawings , in which :

[0049] Figure 1 shows , schematically an overview of a mobile fusion device (MFD) , in accordance with an embodiment o f the present invention; Figure 2 is a schematic flow diagram illustrating an overview of an operational process of the device of Figure 1 ;

[0050] Figure 3 shows the cross-sectional side view with hidden details of the MFD 1 ;

[0051] Figures 4a and 4b and 4c show the cross-sectional side view with hidden details of the MFD reactor 467 of the MFD 1 shown in Figure 3 ;

[0052] Figures 5a and 5b show the cross-sectional side view with hidden details of the MFD support sub-systems 468 of the MFD 1 shown in Figure 3 ;

[0053] Figures 6a and 6b and 6c show the cross-sectional side view with hidden details of the MFD support and fuel inj ection subsystems 469 of the MFD 1 shown in Figure 3 ;

[0054] Figures 7a and 7b show the cross-sectional side view with hidden details of the MFD reactor with internal magnetic field configuration 467A of the MFD 1 shown in Figure 3 ;

[0055] Figure 8 shows a land-based MFD electricity generating power station 562 fitted with a MFD 1A;

[0056] Figure 9 shows a cutaway side view of a large container carrying ship 575 fitted with a MFD IB and a cutaway side view of a submarine 578 fitted with a MFD 1C ;

[0057] Figure 10 shows an overhead external view of a blended wing body BWB aircraft 580 that has an internal centrally mounted MFD ID; and

[0058] Figure 11 shows the external side view of a spacecraft 582 that is fitted with a MFD IE powerplant .

[0059] In the drawings , pipework that contains flowing Helium coolant and flowing liquid metal 17Li- 83Pb are shown as black lines with arrows on them that indicates the direction of flow of the Helium coolant or the flow of the liquid metal 17Li- 83Pb . Black dots on these black lines indicates bends in the pipework and the start and end of straight pipework that may intersect other pipework and which interconnect the subsystems of the MFD . Electrical cabling that interconnects the sub-systems of the MFD 1 are not shown in the drawings .

[0060] Turning to Figure 1 , this shows generally at 1 , a mobile fusion device (MFD) according to an embodiment o f the present invention . The MFD comprises three main sections , the MFD reactor 467 , MFD support sub-systems 468 , and the MFD support and fuel inj ection sub-systems 469 , which are indicated by broken lines in Figure 1 . The MFD reactor 467 is where the Deuterium and Tritium fuel is heated to high enough temperatures and densities and confinement times that fusion occurs , releasing neutrons that are absorbed in and heats up the 17Li- 83Pb breeder blanket where more Tritium fuel is bred and where heat is trans ferred to Helium coolant . The MFD support sub-systems 468 houses auxiliary power units that generate electricity to power the electrical sub-systems of the MFD, and houses the MFD control computer, and where the Helium coolant is cryogenically cooled and puri fied, and where the 17Li- 83Pb breeder blanket fluid is puri fied by separating and storing Deuterium fuel and Tritium fuel and Helium coolant , and where a Helium heat exchanger is located . The MFD support and fuel inj ection sub-systems 469 houses Deuterium and Tritium neutral beam inj ection plasma heating systems and a Deuterium and Tritium fuel gas puf fer system and a Deuterium and Tritium fuel storage and pellet manufacturing system, and where the 17Li- 83Pb breeder blanket fluid is puri fied by separating and storing Deuterium fuel and Tritium fuel and Helium coolant , and where a Helium heat exchanger is located, and where the Helium coolant is cryogenically cooled and puri fied, and houses auxiliary power units that generate electricity to power the electrical sub-systems of the MFD . The MFD is housed within a multi-layered pressurised outer containment pod MLP, which has a multi-layered pressurised rear access hatch MLH . The MFD is mounted on a s liding raft SR for ease of access .

[0061] In the centre is an MFD reactor 467 , including :

[0062] • An MFD reactor outer casing 64

[0063] • Ion cyclotron resonance heating systems 3 , 4 , 5 , 6

[0064] • Magnetic mirror electromagnetic field coils 114 , 160

[0065] • Electron cyclotron resonance heating directable launchers 121 , 122 , 151 , 152

[0066] • Superconducting electromagnetic field coil 135

[0067] • Sweeping electromagnetic field coils 108 , 112

[0068] At a first end are MFD support sub-systems 468 , comprising :

[0069] • Auxiliary power units 195 , 249

[0070] • MFD control computer 198

[0071] • Helium cryogenic cooling plants 201 , 202

[0072] • Tritium cleanup and fuel recovery container outer wall 261

[0073] • Tritium recovery container outer wall 205

[0074] • Helium heat exchanger outer wall 211

[0075] • Vacuum pumping container outer wall 260

[0076] • 17Li- 83Pb Helium separator container outer wall 243

[0077] • Helium Tritium separator container outer wall 231

[0078] At a second end are MFD support and fuel inj ection sub-systems 469 , including : Deuterium neutral beam inj ection heating container 383

[0079] Tritium neutral beam inj ection heating container 309

[0080] • Deuterium and Tritium fuel gas puf fer tube pump 411

[0081] • Deuterium and Tritium fuel storage and pellet manufacturing container 379

[0082] • Vacuum pumping container outer wall 460

[0083] • 17Li- 83Pb Helium separator container outer wall 338

[0084] • Helium Tritium separator container outer wall 331

[0085] • Helium heat exchanger outer wall 347

[0086] • Tritium cleanup and fuel recovery container outer wall 461

[0087] • Tritium recovery container outer wall 358

[0088] • Helium cryogenic cooling plant 373

[0089] • Auxiliary power units 355 , 375 .

[0090] The MFD 1 shown in Figure 3 , and the MFDs 1A, IB, 1C, ID, IE , shown in Figures 8 , 9 , 9 , 10 , 11 , respectively, can achieve Deuterium and Tritium fusion ignition within the MFD reactor 467 with the following thirty stage MFD 1 fusion ignition procedure .

[0091] Stage 1 - External power connection .

[0092] The MFD 1 sub-systems are designed to be powered by its four auxiliary power units 195 , 249 , 355 , 375 , but initially the MFD 1 , as shown in Figure 3 , may require external electrical power to power its sub-systems including the seven plasma heating systems in order to achieve Deuterium and Tritium fusion ignition conditions within the MFD reactor 467 . The auxiliary power units 195 , 249 , 355 , 375 are therefore interconnected with an external power source cable 561 that is attached to an external power source socket 551 , as shown in Figure 3 . The external power source socket 551 could be interconnected to an external electrical power source such as a ground power unit GPU, not shown in Figure 3 .

[0093] Stage 2 - MFD control computer activated .

[0094] The MFD control computer 198 needs to be powered and is used at all times to control and monitor the sub-systems of the MFD 1 .

[0095] Stage 3 - Environmental protection pumps and pressure sensors activated .

[0096] A Helium Tritium separator container (HTSC ) gas pressure device 235 is connected to the MFD control computer 198 that controls the HTSC air pump 234 that pressurises the air in the HTSC inner wall air gap 232 so that any leaking Helium and Tritium or any other impurities from the Helium Tritium separator 236 and the Tritium from the Helium storage system 237 and the impurities from the Helium system 238 and the Helium Tritium separator container interior 239 , cannot permeate freely through the HTSC inner wall 233 .

[0097] Similarly, a HTSC gas pressure device 330 is connected to the MFD control computer 198 that controls the HTSC air pump 329 that pressurises the air in the HTSC inner wall air gap 332 so that any leaking Helium and Tritium or any other impurities from the Helium Tritium separator 335 and the Tritium from Helium storage system 342 and the impurities from the Helium system 344 and the Helium Tritium separator container interior 334 cannot permeate freely through the HTSC inner wall 333 . A 17Li- 83Pb Helium separator container (HSC ) gas pressure device 241 is connected to the MFD control computer 198 that controls the 17Li- 83Pb Helium separator container (HSC ) air pump 240 that pressurises the air in the 17Li- 83Pb HSC inner wall air gap 244 so that any leaking Helium from the 17Li- 83Pb Helium separator 242 and the Helium storage system 246 and the 17Li- 83Pb Helium separator container interior 247 cannot permeate freely through the 17Li- 83Pb HSC inner wall 245 .

[0098] Similarly, a 17Li- 83Pb HSC gas pressure device 337 is connected to the MFD control computer 198 that controls the 17Li- 83Pb HSC air pump 336 that pressurises the air in the 17Li- 83Pb HSC inner wall air gap 339 so that any leaking Helium from the 17Li- 83Pb Helium separator 341 and the Helium storage system 345 and the 17Li- 83Pb Helium separator container interior 343 cannot permeate freely through the 17Li- 83Pb HSC inner wall 340 .

[0099] A Tritium recovery container ( TRC ) gas pressure device 204 is connected to the MFD control computer 198 that controls the TRC air pump 203 that pressurises the air in the TRC inner wall air gap 206 so that any leaking Tritium from the Tritium recovery Vanadium highly permeable membrane container outer wall 221 and the Yttrium solid getter container outer wall 217 and the TRC cryopump 216 and the TRC Tritium storage system 210 and the TRC Tritium delivery system 208 and the Tritium recovery container interior 225 cannot permeate freely through the TRC inner wall 207 .

[0100] Similarly, a TRC gas pressure device 352 is connected to the MFD control computer 198 that controls the TRC air pump 353 that pressurises the air in the TRC inner wall air gap 359 so that any leaking Tritium from the Tritium recovery Vanadium highly permeable membrane container outer wall 362 and the Yttrium solid getter container outer wall 366 and the TRC cryopump 370 and the TRC Tritium storage system 371 and the TRC Tritium delivery system 372 and the Tritium recovery container interior 361 cannot permeate freely through the TRC inner wall 360 .

[0101] A vacuum pumping container (VPC ) gas pressure device 303 is connected to the MFD control computer 198 that controls the VPC air pump 304 that pressurises the air in the VPC air gap 262 so that any leaking Tritium from the VPC upper compartment 308 and the VPC lower compartment 298 cannot permeate freely through the VPC inner wall 264 .

[0102] Similarly, a VPC gas pressure device 412 is connected to the MFD control system 198 that controls the VPC air pump 413 that pressurises the air in the VPC air gap 462 so that any leaking Tritium from the VPC upper compartment 449 and the VPC lower compartment 418 cannot permeate freely through the VPC inner wall 464 .

[0103] A Tritium cleanup and fuel recovery container ( TCFRC ) gas pressure device 254 is connected to the MFD control computer 198 that controls the TCFRC air pump 267 that pressurises the air in the TCFRC air gap 263 so that any leaking Tritium from the TCFRC interior 266 cannot permeate freely through the TCFRC inner wall 265 .

[0104] Similarly, a TCFRC gas pressure device 458 is connected to the MFD control system 198 that controls the TCFRC air pump 459 that pressurises the air in the TCFRC air gap 463 so that any leaking Tritium from the TCFRC interior 466 cannot permeate freely through the TCFRC inner wall 465 .

[0105] A MFD reactor partition (MFDRP ) gas pressure device 248 is connected to the MFD control computer 198 that controls the MFDRP outer wall air pump 227 that pressurises the air in the MFDMFDRP air gap 229 so that any leaking Tritium from the MFD reactor compartment 526 cannot permeate freely through the MFDRP outer wall 228 and the MFDRP inner wall 230 . Similarly, a MFDRP gas pressure device 408 is connected to the MFD control computer 198 that controls the MFDRP outer wall air pump 328 that pressurises the air in the MFDRP air gap 325 so that any leaking Tritium from the MFD reactor compartment 526 cannot permeate freely through the MFDRP outer wall 326 and the MFDRP inner wall 324 .

[0106] MFD casing gas pressure devices 531 , 533 are connected to the fusion control computer 198 that controls the MFD partition outer wall air pumps 527 , 529 , respectively, that are designed to ensure that the air pressure in the MFD inner air gap 547 and the MFD rear domed section inner air gap 548 , respectively, are always greater than the air pressure in the MFD support sub-systems compartment 553 where the MFD support sub-systems 468 of the MFD 1 are located, and the MFD reactor compartment 526 where the MFD reactor 467 of the MFD 1 is located, and the MFD support and fuel inj ection sub-systems compartment 554 where the MFD support and fuel inj ection subsystems 469 of the MFD 1 are located . This is designed to prevent any Tritium leaking from the MFD 1 to the outside environment .

[0107] Similarly, MFD casing gas pressure devices 532 , 534 are connected to the MFD control computer 198 that controls the MFD partition outer wall air pumps 528 , 530 , respectively, that are designed to ensure that the air pressure in the MFD outer air gap 543 and the MFD rear domed section outer air gap 544 , respectively, are always greater than the air pressure in the MFD inner air gap 547 and the MFD rear domed section inner air gap 548 , respectively, so reducing the possibility of any Tritium leaking from the MFD 1 to the outside environment . Stage 4 - Three Helium cryogenic cooling systems activated.

[0108] The Helium cryogenic cooling plants 201, 202, 373, and the Helium cryogenic cooling plant pumps 199, 200, 252, 253, 354, 374 all need to be powered and operational.

[0109] Stage 5 - Twelve Helium coolant pumps activated.

[0110] Mounted equidistantly between the MFD reactor outer casing 64, and the MFD reactor inner vacuum chamber 2, are three concentric layers of Helium cooling tubes 58, 60, 62 that are designed to act as a Helium heat exchanger within the four liquid metal 17Li-83Pb Tritium breeding blanket layers 57, 59, 61, 63, as shown in Figure 3 and Figures 4a and 4b and 4c.

[0111] To maximise the heat transfer to the three concentric layers of Helium, cooling tubes 58, 60, 62, they are arranged in concentric equidistantly spaced rings that are designed to act as a Helium heat exchanger within the four liquid metal 17Li- 83Pb Tritium breeding blanket layers 57, 59, 61, 63. The three concentric layers of Helium cooling tubes 58, 60, 62 are suspended in place to the MFD reactor outer casing 64, using connector arms, which are not shown in Figures 4a and 4b and 4c or Figures 7a and 7b.

[0112] The breeder blanket cool Helium coolant upper pump 68 pumps cooled Helium coolant into the Helium transfer upper inlet pipework 65, 66, 67 and the cooled Helium coolant absorbs heat energy from the four liquid metal 17Li-83Pb Tritium breeding blanket layers 57, 59, 61, 63 as the cooled Helium coolant travels through the three concentric layers of Helium cooling tubes 58, 60, 62, respectively, bi-directionally and downwards, as shown in Figures 4a and 4b and 4c. The heated Helium coolant in the three concentric layers of Helium cooling tubes 58, 60, 62 eventually reaches the Helium transfer lower outlet pipework 70, 71, 72 and the Helium transfer lower outlet pipework 73, 74, 75 which is transferred by pipework to the breeder blanket heated Helium coolant upper pump 69 and the breeder blanket heated Helium coolant lower pump 76, respectively.

[0113] Similarly, the breeder blanket cool Helium coolant lower pump 77 pumps cooled Helium coolant into the Helium transfer upper inlet pipework 78, 79, 80 and the cooled Helium coolant absorbs heat energy from the four liquid metal 17Li-83Pb Tritium breeding blanket layers 57, 59, 61, 63 as the cooled Helium coolant travels through the three layers of Helium cooling tubes 58, 60, 62, respectively, bi-directionally and downwards, as shown in Figures 4a and 4b and 4c. The heated Helium coolant in the three concentric layers of Helium cooling tubes 58, 60, 62 eventually reaches the Helium transfer lower outlet pipework 70, 71, 72 and the Helium transfer lower outlet pipework 73, 74, 75 which is transferred by pipework to the breeder blanket heated Helium coolant upper pump 69 and the breeder blanket heated Helium coolant lower pump 76, respectively, as shown in Figures 4a and 4b and 4c.

[0114] The primary divertor cool Helium coolant upper pump 32 pumps cooled Helium coolant into the primary divertor cool Helium coolant target inlet pipe 31 and the primary divertor cool Helium coolant central dome inlet pipe 30 and downwards and around the concentrically arranged and interconnected primary divertor Helium cooled Tungsten backplates 7, and the primary divertor Helium cooled Tungsten energy dump targets 8, and the primary divertor Helium cooled Tungsten power exhaust and momentum loss region targets 9, and the primary divertor Helium cooled Tungsten baffles 10, and the primary divertor Helium cooled Tungsten central dome 11, and the primary divertor Helium cooled Tungsten backplate central dome 13 , and the primary divertor Helium cooled Tungsten central dome power exhaust and momentum loss region targets 15 , and the primary divertor transparent liner pumping plate 16 , and the primary divertor Helium cooled Tungsten central dome power exhaust and momentum loss region target backplates 19 , and the primary divertor Helium cooled pumping channels 18 , 29 , and the primary divertor vacuum chamber pumping channels 33 , that collectively create the circular cross-section gas target primary divertor . The primary divertor heated Helium coolant lower pump 22 pumps heated Helium coolant out through the primary divertor heated Helium coolant target outlet pipe 20 and the primary divertor heated Helium coolant central dome outlet pipe 21 , as shown in Figures 4a and 4b and 4c .

[0115] The secondary divertor cool Helium coolant upper pump 48 pumps cooled Helium coolant into the secondary divertor cool Helium coolant target inlet pipe 49 and the secondary divertor cool Helium coolant central dome inlet pipe 50 and downwards and around the concentrically arranged and interconnected secondary divertor Helium cooled Tungsten backplates 34 , and the secondary divertor Helium cooled Tungsten energy dump targets 36 , and the secondary divertor Helium cooled Tungsten power exhaust and momentum loss region targets 37 , and the secondary divertor Helium cooled Tungsten baf fles 38 , and the secondary divertor Helium cooled Tungsten central dome 12 , and the secondary divertor Helium cooled Tungsten backplate central dome 14 , and the secondary divertor Helium cooled Tungsten central dome power exhaust and momentum loss region targets 40 , and the secondary divertor Helium cooled transparent liner pumping plate 17 , and the secondary divertor Helium cooled Tungsten central dome power exhaust and momentum loss region target backplates 35 , and the secondary divertor Helium cooled pumping channels 41 , 42 , that collectively create the circular cross-section gas target secondary divertor. The secondary divertor heated Helium coolant lower pump 45 pumps heated Helium coolant out through the secondary divertor heated Helium coolant target outlet pipe 46 and the secondary divertor heated Helium coolant central dome outlet pipe 47, as shown in Figures 4a and 4b and 4c.

[0116] Stage 6 - Four 17Li-83Pb breeder blanket pumps activated.

[0117] The breeder blanket pure liquid metal 17Li-83Pb (LMLi-Pb) upper pump 87 pumps LMLi-Pb that has had Tritium, Helium and other impurities removed, into the LMLi-Pb transfer lower inlet pipework 100, 101, 102, 103, 104. The LMLi-Pb then travels bi-directionally and upwards through the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63 and transfers its heat energy to the cooled Helium coolant that travels through the three concentric layers of Helium cooling tubes 58, 60, 62, as shown in Figures 4a and 4b and 4c. The cooled LMLi-Pb in the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63 eventually reaches the LMLi-Pb transfer upper outlet pipework 81, 82, 83, 84, 85 and the LMLi-Pb transfer upper outlet pipework 88, 89, 90, 91, 92 which is transferred by pipework to the the breeder blanket impure LMLi-Pb upper pump 86 and the breeder blanket impure LMLi-Pb lower pump 99, as shown in Figures 4a and 4b and 4c. The cooled impure LMLi-Pb that has passed through the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63 that is pumped by the breeder blanket impure LMLi-Pb upper pump 86 and the breeder blanket impure LMLi-Pb lower pump 99 will have Tritium and Helium and other impurities in it that have been produced from the neutron bombardment of the cooled LMLi-Pb in the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63. Similarly, the breeder blanket pure LMLi-Pb lower pump 98 pumps LMLi-Pb that has had Tritium, Helium and other impurities removed, into the LMLi-Pb transfer lower inlet pipework 93, 94, 95, 96, 97. The LMLi-Pb then travels bidirectionally and upwards through the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63 and transfers its heat energy to the cooled Helium coolant that travels through the three concentric layers of Helium cooling tubes 58, 60, 62, as shown in Figures 4a and 4b and 4c. The cooled LMLi-Pb in the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63 eventually reaches the LMLi-Pb transfer upper outlet pipework 81, 82, 83, 84 85 and the LMLi-Pb transfer upper outlet pipework 88, 89, 90, 91, 92 which is transferred by pipework to the breeder blanket impure LMLi-Pb upper pump 86 and the breeder blanket impure LMLi-Pb lower pump 99, respectively, as shown in Figures 4a and 4b and 4c. The cooled impure LMLi-Pb that has passed through the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63 that is pumped from the breeder blanket impure LMLi-Pb upper pump 86 and the breeder blanket impure LMLi-Pb lower pump 99 will have Tritium and Helium and other impurities in it that have been produced from the neutron bombardment of the cooled LMLi-Pb in the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63.

[0118] The LMLi-Pb transfer lower inlet pipework 93, 94, 95, 96, 97 and the LMLi-Pb transfer lower inlet pipework 100, 101, 102, 103, 104 are collectively designed to fill and circulate the LMLi-Pb breeder blanket from the bottom upwards, towards the LMLi-Pb transfer upper outlet pipework 81, 82, 83, 84, 85 and the LMLi-Pb transfer upper outlet pipework 88, 89, 90, 91, 92, so assisting to reduce pressure drops induced by magnetohydrodynamics but also importantly to prevent the accumulation of Helium gas bubbles and Helium gas gap pockets, produced by the neutron bombardment of Lithium in the LMLi-Pb breeder blanket into Tritium fuel and Helium gas , in the upper hal f of the LMLi-Pb breeder blanket .

[0119] Stage 7 . 1 - First outer fuel cycle systems activated .

[0120] The MFD 1 shown in Figure 3 dual outer fuel cycle design feature involves a first outer fuel cycle system which is shown in Figures 5a and 5b . It involves the LMLi-Pb that has Tritium, Helium and other impurities in it which is trans ferred by pipework by the breeder blanket impure LMLi-Pb upper pump 86 to the 17Li- 83Pb Helium separator 242 . Helium ( in the form of Helium-4 or Helium-3 ) has very low solubility in the LMLi-Pb that has Tritium, Helium and other impurities in it . This means that there can be a very high separation ef ficiency of Helium from the low-pressure loop by desorption in the form of Helium bubbles , not shown in Figures 5a and 5b, located within the 17Li- 83Pb Helium separator 242 . I f the volume flow rate of the LMLi-Pb that has Tritium, Helium and other impurities in it is maximised by the breeder blanket impure LMLi-Pb upper pump 86 to the 17Li- 83Pb Helium separator 242 , then the Helium gas in dissolved form will be maximised within the LMLi-Pb that has Tritium, Helium and other impurities in it . As the LMLi-Pb that has Tritium, Helium and other impurities in it is pumped into the low pressure loop, not shown in Figures 5a and 5b, located within the 17Li- 83Pb Helium separator 242 , Helium bubbles will be generated in the low pressure loop by desorption in the 17Li- 83Pb Helium separator 242 , as the solubility limit of the Helium gas is decreased in the LMLi-Pb that has Tritium, Helium and other impurities in it with decreasing pressure .

[0121] The first outer fuel cycle system of the cross-sectional side view with hidden details of the MFD support sub-systems 468 of the MFD 1 , as shown in Figures 5a and 5b, also involves the heated Helium coolant that is trans ferred by pipework by the breeder blanket heated Helium coolant lower pump 76 to the Helium Tritium separator 236 , as shown in Figures 5a and 5b . Helium gas containing Tritium gas produced by the 17Li- 83Pb Helium separator 242 is then trans ferred by pipework to the Helium Tritium separator 236 . The removal of Tritium from Helium can be accomplished by selective absorption at room or cryogenic temperatures onto molecular sieve beds . Molecular sieve beds within the Helium Tritium separator 236 can treat high flow rates of Helium gas containing Tritium and other impurities , which can assist to increase the Tritium inventory trans ferred by pipework and stored in the Tritium from Helium storage system 237 . Other impurities that are separated from the Helium gas by the molecular sieve beds within the Helium Tritium separator 236 are trans ferred by pipework to the impurities from Helium system 238 .

[0122] Helium from the Helium Tritium separator 236 is then trans ferred by pipework to the Helium storage system 246 and is then trans ferred by pipework to the main Helium storage system 255 , as shown in Figures 5a and 5b . Tritium from the Helium Tritium separator 236 is then trans ferred by pipework to the Tritium from Helium storage system 237 and is then trans ferred by pipework to the Tritium storage system 258 and is then trans ferred by pipework to the TRC Tritium storage system 210 , as shown in Figures 5a and 5b .

[0123] The first outer fuel cycle system also involves the 17Li- 83Pb with Tritium and other impurities in it , which is then trans ferred by pipework from the 17Li- 83Pb Helium separator 242 and flows over the Vanadium high permeable membrane 223 . The Vanadium high permeable membrane 223 has a high permeability of Tritium and must be of suf ficient surface area and thickness for structural strength reasons and to maximise the permeability of the Tritium into the TRC Tritium interior 222 . The TRC Tritium interior 222 needs to be maintained at a lower vacuum pressure than the Tritium recovery Vanadium highly permeable membrane container interior 224 to maximise the pressure di f ferential and to maximise the Tritium permeation between the two sides of the Vanadium high permeable membrane 223 .

[0124] The Tritium gas in the TRC Tritium interior 222 is then trans ferred by pipework into one of the three stacked Yttrium solid getter beds 220 . The sponge form of Yttrium metal has a very high af finity for Hydrogen isotopes such as Tritium, with the three stacked Yttrium solid getter beds 220 being used alternately in three modes which are the operational mode , where Tritium gas in the TRC Tritium interior 222 would be trans ferred by pipework through the Tritium recovery Vanadium highly permeable membrane container outer wall 221 and through the Yttrium solid getter container outer wall 217 and into one of the three stacked Yttrium solid getter beds 220 where the sponge form of the Yttrium metal would extract Tritium . During the regenerative mode , one of the three stacked Yttrium solid getter beds 220 would be heated to , say, 1000 ° C and the Tritium gas released would pass through the Niobium wall 218 and into the low pressure Yttrium solid getter container Tritium interior 219 . During the standby mode , one of the three stacked Yttrium solid getter beds 220 would be allowed to cool down after having been heated to , say, 1000 ° C during the regenerative mode .

[0125] The Tritium gas accumulated in the low-pressure Yttrium solid getter container Tritium interior 219 would then be trans ferred by pipework through the Yttrium solid getter container outer wall 217 and into the TRC cryopump 216 . The Tritium is then trans ferred by pipework to the TRC Tritium storage system 210 and is then trans ferred by pipework to the TRC Tritium delivery system 208 , as shown in Figures 5a and 5b . Tritium can then be inj ected back into the MFD reactor 467 as millimeter-si zed frozen Tritium pellets that are fired at high speeds of up to several thousand km / h from the Deuterium and Tritium fuel storage and pellet manufacturing inj ection tube 55 or can be inj ected back into the MFD reactor 467 as Tritium neutral particles using the Tritium neutral beam inj ection heater .

[0126] Stage 7 .2 - Second outer fuel cycle systems activated .

[0127] The MFD 1 ( shown in Figure 3 ) dual outer fuel cycle design feature involves a second outer fuel cycle system which is shown in Figures 6a and 6b and 6c . It involves the LMLi-Pb that has Tritium, Helium and other impurities in it which is trans ferred by pipework by the breeder blanket impure LMLi-Pb lower pump 99 to the 17Li- 83Pb Helium separator 341 . Helium has very low solubility in the LMLi-Pb . This means that there can be a very high separation ef ficiency of Helium from the low-pressure loop by desorption in the form of Helium bubbles , not shown in Figures 6a and 6b and 6c, located within the 17Li- 83Pb Helium separator 341 . I f the volume flow rate of the LMLi-Pb is maximised by the breeder blanket impure LMLi-Pb lower pump 99 to the 17Li- 83Pb Helium separator 341 , then the Helium gas in dissolved form will be maximised within the LMLi-Pb that has Tritium, Helium and other impurities in it . As the LMLi-Pb is pumped into the low pressure loop, not shown in Figures 6a and 6b and 6c, located within the 17Li- 83Pb Helium separator 341 , Helium bubbles will be generated in the low pressure loop by desorption in the 17Li- 83Pb Helium separator 341 , as the solubility limit of the Helium gas is decreased in the LMLi-Pb, with decreasing pressure . The second outer fuel cycle system shown in the cross- sectional side view with hidden details of the MFD support and fuel inj ection sub-systems 469 of the MFD 1 , as shown in Figures 6a and 6b and 6c, also involves the heated Helium coolant that is trans ferred by pipework by the breeder blanket heated Helium coolant upper pump 69 to the Helium Tritium separator 335 , as shown in Figures 6a and 6b and 6c . Helium gas containing Tritium gas produced by the 17Li- 83Pb Helium separator 341 is then trans ferred by pipework to the Helium Tritium separator 335 . The removal of Tritium from Helium can be accomplished by selective absorption at room or cryogenic temperatures onto molecular sieve beds . Molecular sieve beds within the Helium Tritium separator 335 can treat high flow rates of Helium gas containing Tritium gas and other impurities , which can assist to increase the Tritium inventory trans ferred by pipework and stored in the Tritium from Helium storage system 342 . Other impurities that are separated from the Helium gas by the molecular sieve beds within the Helium Tritium separator 335 are trans ferred by pipework to the impurities from Helium system 344 .

[0128] Helium from the Helium Tritium separator 335 is then trans ferred by pipework to the Helium storage system 345 and is then trans ferred by pipework to the main Helium storage system 457 , as shown in Figures 6a and 6b and 6c . Tritium from the Helium Tritium separator 335 is then trans ferred by pipework to the Tritium from Helium storage system 342 and is then trans ferred by pipework to the Tritium storage system 454 and is then trans ferred by pipework to the TRC Tritium storage system 371 , as shown in Figures 6a and 6b and 6c .

[0129] The heated Helium coolant that exits the heated Helium outlet 322 and the heated Helium outlet 410 and the heated Helium outlet 401 will all have Tritium and other impurities in it , are then trans ferred by pipework by the breeder blanket heated Helium coolant upper pump 69 to the Helium Tritium separator 335 , as shown in Figures 6a and 6b and 6c .

[0130] The second outer fuel cycle system also involves the 17Li- 83Pb with Tritium and other impurities in it , which is then trans ferred by pipework from the 17Li- 83Pb Helium separator 341 and flows over the Vanadium high permeable membrane 364 . The Vanadium high permeable membrane 364 has a high permeability of Tritium and must be of suf ficient surface area and thickness for structural strength reasons and to maximise the permeability of the Tritium into the TRC Tritium interior 365 . The TRC Tritium interior 365 needs to be maintained at a lower vacuum pressure than the Tritium recovery Vanadium highly permeable membrane container interior 363 to maximise the pressure di f ferential and to maximise the Tritium permeation between the two sides of the Vanadium high permeable membrane 364 .

[0131] The Tritium gas in the TRC Tritium interior 365 is then trans ferred by pipework into one of the three stacked Yttrium solid getter beds 367 . The sponge form of Yttrium metal has a very high af finity for Hydrogen isotopes such as Tritium, with the three stacked Yttrium solid getter beds 367 , being used alternately in three modes which are operational mode , where Tritium gas in the TRC Tritium interior 365 would be trans ferred by pipework through the Tritium recovery Vanadium highly permeable membrane container outer wall 362 and through the Yttrium solid getter container outer wall 366 and into one of the three stacked Yttrium solid getter beds 367 , where the sponge form of the Yttrium metal would extract Tritium . During the regenerative mode , one of the three stacked Yttrium solid getter beds 367 , would be heated to , say, 1000 ° C and the Tritium gas released would pass through the Niobium wall 368 and into the low pressure Yttrium solid getter container Tritium interior 369 . During the standby mode , one of the three stacked Yttrium solid getter beds 367 would be allowed to cool down after having been heated to , say, 1000 ° C during the regenerative mode .

[0132] The Tritium gas that accumulates in the low-pressure Yttrium solid getter container Tritium interior 369 would then be trans ferred by pipework through the Yttrium solid getter container outer wall 366 and into the TRC cryopump 370 . The Tritium is then trans ferred by pipework to the TRC Tritium storage system 371 and is then trans ferred by pipework to the TRC Tritium delivery system 372 , as shown in Figures 6a and 6b and 6c, and Tritium can then be inj ected back into the MFD reactor 467 as millimeter-si zed frozen Tritium pellets that are fired at high speeds of up to several thousand km / h from the Deuterium and Tritium fuel storage and pellet manufacturing inj ection tube 55 or can be inj ected back into the MFD reactor 467 as Tritium neutral particles using the Tritium neutral beam inj ection heater . .

[0133] Stage 8 . 1 - First direct internal recycling systems activated .

[0134] The MFD 1 shown in Figure 3 has two separate low pressure vacuum pumping systems and two direct internal recycling fuel systems that need to be powered and operational .

[0135] Figures 5a and 5b shows the cross-sectional side view with hidden details of the MFD support sub-systems 468 of the MFD 1 shown in Figure 3 , and shows that a metal foil pump (MFR ) is connected to two linear di f fusion pumps and two liquid ring pumps .

[0136] Argon, Helium and other impurities are pumped out through the primary divertor Helium cooled pumping channels 18 , 29 , and out through the primary divertor Helium cooled transparent liner pumping plate 16 and out through the primary divertor vacuum chamber pumping pipework 23 that is connected to the MFP inlet 291 , as shown in Figures 4a and 4b and 4c and Figures 5a and 5b .

[0137] The MFP and linear di f fusion pumps outer container 307 has an upper surface that has a MFP inlet 291 . Gases from the primary divertor vacuum chamber pumping pipework 23 are pumped into the MFP inlet 291 and down into the MFP upper chamber 290 where Hydrogen gas and Hydrogen isotopes are pumped and separated out and flows out of the MFP upper chamber side port 284 . The MFP central chamber 288 then pumps and separates out pure Deuterium and Tritium fuel that flows out of the MFP central chamber side port 297 . The remaining Hel ium and other impurities are then pumped into the MFP lower chamber 285 that pumps and separates out the impurities that flows out of the MFP lower chamber side port 286 .

[0138] The MFP consisting of the upper surface that has a MFP inlet 291 , MFP upper chamber 290 , MFP upper chamber side port 284 , MFP central chamber 288 , MFP central chamber side port 297 , MFP lower chamber 285 and the MFP lower chamber side port 286 , is a continuously operational vacuum pumping method that does not have any moving components and which provides vacuum pumping and is able to separate out and compress and pump out only Hydrogen and Deuterium and Tritium and impurities . Unfortunately, the MFP cannot vacuum pump and separate out , and cannot compress , any other gases such as Helium and impurities that enter the upper surface that has a MFP inlet 291 from the interconnected primary divertor vacuum chamber pumping pipework 23 . Consequently, the MFP cannot be used on its own for the primary vacuum pumping of the MFD reactor 467 of the mobile fusion device 1 shown in Figure 3 . MFPs , therefore , have to be used in combination with another interconnected continuously operational primary vacuum pumping system that can provide additional vacuum pumping and is able to separate out and compress and pump out Helium and other impurities . A primary vacuum pumping linear di f fusion pump in series with a rough pumping liquid ring pump, as shown in Figures 5a and 5b, will collectively allow the vacuum pumping and gas separation of Helium and other impurities required for the MFD reactor 467 of the mobile fusion device 1 . The primary vacuum pumping linear di f fusion pump is also required as the MFP will most likely not be able to operate in the vacuum conditions created only by the rough vacuum pumping liquid ring pump .

[0139] Another advantage of the primary vacuum pumping linear di f fusion pump and the rough vacuum pumping liquid ring pump when used in the mobile fusion device 1 is that Mercury is the working fluid for the primary vacuum pumping linear di f fusion pump and the rough vacuum pumping liquid ring pump . Mercury is very beneficial as it is fully Tritium compatible and will not be activated by neutronic radiation produced by fusion reactions in the MFD reactor 467 of the mobile fusion device 1 shown in Figure 3 .

[0140] The MFP central chamber 288 that pumps and separates out pure Deuterium and Tritium fuel and which flows out of the MFP central chamber side port 297 , is then pumped into the righthand linear di f fusion pump first baf fle 296 . The right-hand linear di f fusion pump first baf fle 296 needs to be kept cool at about 190K by a compressed gas coolant system 283 that is located in the vacuum pumping container (VPC ) lower compartment 298 . The pure Deuterium and Tritium fuel is then pumped downwards from the right-hand linear di f fusion pump first baf fle 296 and into the right-hand linear di f fusion pump second baf fle 295 . The right-hand linear di f fusion pump second baf fle 295 needs to be kept cool at about 220K by a compressed gas coolant system 287 that is located in the VPC lower compartment 298 . A partition floor 268 separates the VPC lower compartment 298 from the VPC upper compartment 308 . The pure Deuterium and Tritium fuel is then pumped downwards from the right-hand linear di f fusion pump second baf fle 295 and into the righthand linear di f fusion pump main chamber 294 . Below the righthand linear di f fusion pump main chamber 294 is the right-hand linear di f fusion pump wall cooling system 293 . The right-hand linear di f fusion pump wall cooling system 293 needs to be kept cool at about 280K by a cooling water system 306 that i s located in the VPC lower compartment 298 . Below the right-hand linear di f fusion pump wall cooling system 293 is the righthand linear di f fusion pump Mercury boiler 292 . The right-hand linear di f fusion pump Mercury boiler 292 needs to be kept hot at about 450K by a compressed gas heating system 289 that is located in the VPC lower compartment 298 .

[0141] The pure Deuterium and Tritium fuel is then trans ferred by pipework from the right-hand linear di f fusion pump main chamber 294 to the right-hand l iquid ring pump main chamber 300 . The right-hand liquid ring pump main chamber 300 needs to be kept cool by a Mercury cooler system 299 . The Mercury cooler system 299 needs to be kept cool at about 280K by the cooling water system 306 that is located in the VPC lower compartment 298 .

[0142] The pure Deuterium and Tritium fuel is then trans ferred by pipework from the right-hand liquid ring pump main chamber 300 to the right-hand liquid ring pump gas cooler 305 . The righthand liquid ring pump gas cooler 305 is interconnected by pipework to the cooling water system 306 that is located in the VPC lower compartment 298 . The right-hand liquid ring pump gas cooler 305 assists in keeping the water cool at about 280K that is used in the cooling water system 306 .

[0143] The right-hand liquid ring pump gas cooler 305 is interconnected by pipework to the compressed gas coolant system 301 that is located in the VPC lower compartment 298 . The right-hand liquid ring pump gas cooler 305 assists in keeping the compressed gas cool at about 190K that is used in the compressed gas coolant system 301 .

[0144] The right-hand liquid ring pump gas cooler 305 is also interconnected by pipework to the compressed gas coolant system 302 that is located in the VPC lower compartment 298 . The right-hand liquid ring pump gas cooler 305 assists in keeping the compressed gas cool at about 220K that is used in the compressed gas coolant system 302 .

[0145] Stage 8 .2 - Second direct internal recycling systems activated .

[0146] Figures 6a and 6b and 6c is a cross-sectional side view with hidden details of the MFD support and fuel inj ection subsystems 469 of the mobile fusion device 1 , and shows that a MFP is connected to two linear di f fusion pumps and two liquid ring pumps .

[0147] Argon, Helium and other impurities are pumped out through the secondary divertor vacuum chamber pumping channels , 39 , and out through the secondary divertor Helium cooled transparent liner pumping plate 17 and out through the secondary divertor vacuum chamber pumping pipework 24 that is connected to the MFP inlet 447 , as shown in Figure 3 and in Figures 6a and 6b and 6c .

[0148] The secondary divertor vacuum chamber pumping pipework 24 is interconnected to the vacuum pumping pipework that is attached to the Deuterium neutral beam inj ection heating container 383 , and is also interconnected to the vacuum pumping pipework that is attached to the Tritium neutral beam inj ection heating container 309 . The MFP and linear di f fusion pumps outer container 448 has an upper surface that has an MFP inlet 447 . Gases from the secondary divertor vacuum chamber pumping pipework 24 are pumped into the MFP inlet 447 and down into the MFP upper chamber 446 where Hydrogen gas and Hydrogen isotopes are pumped and separated out and flows out of the MFP upper chamber side port 445 . The MFP central chamber 444 then pumps and separates out pure Deuterium and Tritium fuel that flows out of the MFP central chamber side port 443 . The remaining Helium and other impurities are then pumped into the MFP lower chamber 441 that pumps and separates out the impurities that flows out of the MFP lower chamber side port 442 .

[0149] The MFP consisting of the upper surface that has a MFP inlet 447 , MFP upper chamber 446 , MFP upper chamber side port 445 , MFP central chamber 444 , MFP central chamber side port 443 , MFP lower chamber 441 and the MFP lower chamber side port 442 is a continuously operational vacuum pumping method that does not have any moving components , and which provides vacuum pumping and is able to separate out and compress and pump out only Hydrogen and Deuterium and Tritium and impurities . Unfortunately, the MFP cannot vacuum pump and separate out and cannot compress any other gases such as Helium and impurities that enter the upper surface that has a MFP inlet 447 from the interconnected secondary divertor vacuum chamber pumping pipework 24 . Consequently, the MFP cannot be used on its own for the primary vacuum pumping of the mobile fusion device 1 shown in Figure 3 . The MFP therefore has to be used in combination with another interconnected continuously operational primary vacuum pumping system that can provide additional vacuum pumping and is able to separate out and compress and pump out Helium and other impurities . A primary vacuum pumping linear di f fusion pump in series with a rough pumping liquid ring pump, as shown in Figures 6a and 6b and 6c, will collectively allow the vacuum pumping and gas separation of Helium and other impurities required for the mobile fusion device 1. The primary vacuum pumping linear diffusion pump is also required as the MFP will most likely not be able to operate in the vacuum conditions created only by the rough vacuum pumping liquid ring pump.

[0150] The MFP central chamber 444 that pumps and separates out pure Deuterium and Tritium fuel and which flows out of the MFP central chamber side port 443, is then pumped into the lefthand linear diffusion pump first baffle 432. The left-hand linear diffusion pump first baffle 432 needs to be kept cool at about 190K by a compressed gas coolant system 426 that is located in the VPC lower compartment 418. The pure Deuterium and Tritium fuel is then pumped downwards from the left-hand linear diffusion pump first baffle 432 and into the left hand linear diffusion pump second baffle 431. The left-hand linear diffusion pump second baffle 431 needs to be kept cool at about 220K by a compressed gas coolant system 423 that is located in the VPC lower compartment 418. A partition floor 419 separates the VPC lower compartment 418 from the VPC upper compartment 449. The pure Deuterium and Tritium fuel is then pumped downwards from the left-hand linear diffusion pump second baffle 431 and into the left hand linear diffusion pump main chamber 430. Below the left-hand linear diffusion pump main chamber 430 is the left-hand linear diffusion pump wall cooling system 425. The left-hand linear diffusion pump wall cooling system 425 needs to be kept cool at about 280K by a cooling water system 417 that is located in the VPC lower compartment 418. Below the left-hand linear diffusion pump wall cooling system 425 is the left hand linear diffusion pump Mercury boiler 424. The left-hand linear diffusion pump Mercury boiler 424 needs to be kept hot at about 450K by a compressed gas heating system 422 that is located in the VPC lower compartment 418. The pure Deuterium and Tritium fuel is then trans ferred by pipework from the left-hand linear di f fusion pump main chamber 430 and into the left hand liquid ring pump main chamber 421 . The left-hand liquid ring pump main chamber 421 needs to be kept cool by a Mercury cooler system 420 . The Mercury cooler system 420 needs to be kept cool at about 280K by a cooling water system 417 that is located in the VPC lower compartment 418 .

[0151] The pure Deuterium and Tritium fuel is then trans ferred by pipework from the left-hand liquid ring pump main chamber 421 to the left hand liquid ring pump gas cooler 416 . The lefthand liquid ring pump gas cooler 416 is interconnected by pipework to the cooling water system 417 that is located in the VPC lower compartment 418 . The left-hand liquid ring pump gas cooler 416 assists in keeping the water cool at about 280K that is used in the cooling water system 417 .

[0152] The left-hand liquid ring pump gas cooler 416 is interconnected by pipework to the compressed gas coolant system 415 that is located in the VPC lower compartment 418 . The left-hand liquid ring pump gas cooler 416 assists in keeping the compressed gas cool at about 190K that is used in the compressed gas coolant system 415 .

[0153] The left-hand liquid ring pump gas cooler 416 is also interconnected by pipework to the compressed gas coolant system 414 that is located in the VPC lower compartment 418 . The left-hand liquid ring pump gas cooler 416 assists in keeping the compressed gas cool at about 220K that is used in the compressed gas coolant system 414 .

[0154] The left-hand liquid ring pump gas cooler 416 is also used to cool the Deuterium and Tritium fuel that is trans ferred by pipework to the Deuterium and Tritium fuel gas puf fer tube pump 411 . The right-hand liquid ring pump gas cooler 305 is also used to cool the Deuterium and Tritium fuel that is trans ferred by pipework to the Deuterium and Tritium fuel gas puf fer tube pump 411 .

[0155] The mobile fusion device 1 shown in Figure 3 therefore has a dual direct internal recycling design feature which means that Deuterium and Tritium fuel from the left-hand liquid ring pump gas cooler 416 , as shown in Figures 6a and 6b and 6c, and from the right-hand liquid ring pump gas cooler 305 , as shown in Figures 5a and 5b, can both be used to cool the Deuterium and Tritium fuel that is trans ferred by pipework to the Deuterium and Tritium fuel gas puf fer tube pump 411 that is in close proximity to the MFD reactor 467 of the mobile fusion device 1 . This means that a large quantity of unused Deuterium and Tritium fuel can be recycled as close to the MFD 467 of the mobile fusion device 1 as possible , so reducing Deuterium and Tritium throughput and so lowering the inventory of Deuterium and Tritium required for the steady state fusion operation of the mobile fusion device 1 .

[0156] Stage 9 - Deuterium and Tritium gas puffer systems activated .

[0157] The left-hand liquid ring pump gas cooler 416 , as shown in Figures 6a and 6b and 6c, is also used to cool the Deuterium and Tritium fuel that is trans ferred by pipework to the Deuterium and Tritium fuel gas puf fer tube pump 411 . The right-hand liquid ring pump gas cooler 305 , as shown in Figures 5a and 5b, is also used to cool the Deuterium and Tritium fuel that is trans ferred by pipework to the Deuterium and Tritium fuel gas puf fer tube pump 411 . The Deuterium and Tritium fuel gas puf fer tube pump 411 pumps the Deuterium and Tritium fuel gas through pipework that passes through the side of the Deuterium and Tritium fuel storage and pellet manufacturing container 379 and into the Deuterium and Tritium fuel storage and pellet manufacturing container interior 403 , and is attached to the end of the Deuterium and Tritium gas puf fing inj ection tube 56 that is releasably and securely attached at one end to the MFD reactor inner vacuum chamber 2 so that the Deuterium and Tritium fuel gas can be pumped into the MFD reactor 467 of the mobile fusion device 1 to fuel the Deuterium and Tritium fusion reactions when controlled by the MFD control computer 198 .

[0158] In order to minimi ze the amount of expensive Tritium required to start the MFD 1 , the much cheaper Deuterium could be used as Deuterium-Deuterium fusion reactions , since Deuterium exists naturally in water, and to gradually build up in preparation for the Deuterium-Tritium plasma fusion reactions within the MFD reactor 467 . Tritium will then be produced through two pathways , firstly by the 2 . 45MeV neutrons produced by Deuterium+Deuterium = Helium-3+neutron and the neutrons are able to react with the Lithium- 6 of the 17Li- 83Pb breeder blanket to produce Tritium which can be accumulated in preparation for the Deuterium-Tritium fusion fuel requirements for the next step ; and some Tritium will be generated inside the MFD reactor 467 through the Deuterium+Deuterium = Tritium+proton reactions which will fuse with the Deuterium to produce 14 . 1MeV neutrons to enhance the Tritium production within the 17Li- 83Pb breeder blanket .

[0159] Stage 10 . 1 - First inner fuel cycle systems activated .

[0160] The MFD 1 shown in Figure 3 also has two separate inner fuel cycle systems that need to be powered and operational .

[0161] One of the two inner fuel cycles is shown in the cross- sectional side view with hidden details of the MFD support sub-systems 468 of the MFD 1 , as shown in Figures 5a and 5b, and involves the primary divertor vacuum chamber pumping pipework 23 that passes into the VPC upper compartment 308 . The MFP and linear diffusion pumps outer container 307 has an upper surface that has a MFP inlet 291. Gases from the primary divertor vacuum chamber pumping pipework 23 are pumped into the MFP inlet 291 and down into the MFP upper chamber 290. The MFP upper chamber 290 is where Hydrogen gas and Hydrogen isotopes are pumped and separated out and flows out of the MFP upper chamber side port 284. The Helium and other impurities are pumped into the MFP lower chamber 285 that pumps and separates out Helium and other impurities that flows out of the MFP lower chamber side port 286. The Hydrogen gas and Hydrogen isotopes, Helium and other impurities are then pumped into the left hand linear diffusion pump first baffle 282 that needs to be kept cool at about 190K by a compressed gas coolant system 281 that is located in the VPC lower compartment 298.

[0162] A partition floor 268 separates the VPC lower compartment 298 from the VPC upper compartment 308.

[0163] The Hydrogen gas and Hydrogen isotopes, Helium and other impurities are then pumped downwards from the left hand linear diffusion pump first baffle 282 and into the left hand linear diffusion pump second baffle 280. The left hand linear diffusion pump second baffle 280 needs to be kept cool at about 220K by a compressed gas coolant system 278 that is located in the VPC lower compartment 298. The Hydrogen gas and Hydrogen isotopes, Helium and other impurities are then pumped downwards from the left hand linear diffusion pump second baffle 280 and into the left hand linear diffusion pump main chamber 279. Below the left hand linear diffusion pump main chamber 279 is the left hand linear diffusion pump wall cooling system 277. The cooling system 277 needs to be kept cool at about 280K by a cooling water system 272 that is located in the VPC lower compartment 298. Below the left hand linear diffusion pump wall cooling system 277 is the left hand linear di f fusion pump Mercury boiler 276 . The Mercury boiler 276 needs to be kept hot at about 450K by a compressed gas heating system 275 that is located in the VPC lower compartment 298 .

[0164] The Hydrogen gas and Hydrogen isotopes , Helium and other impurities are then trans ferred by pipework from the left hand linear di f fusion pump main chamber 279 to the left hand liquid ring pump main chamber 274 . The ring pump main chamber 274 needs to be kept cool by a Mercury cooler system 273 . The Mercury cooler system 273 needs to be kept cool at about 280K by a cooling water system 272 that is located in the VPC lower compartment 298 . The Hydrogen gas and Hydrogen isotopes , Helium and other impurities are then trans ferred by pipework from the left hand liquid ring pump main chamber 274 to the left hand liquid ring pump gas cooler 271 . The pump gas cooler

[0165] 271 is interconnected by pipework to the cooling water system

[0166] 272 that is located in the VPC lower compartment 298 . The left hand liquid ring pump gas cooler 271 assists in keeping the water cool at about 280K that is used in the cooling water system 272 . The cooler 271 is interconnected by pipework to the compressed gas coolant system 270 that is located in the VPC lower compartment 298 . The cooler 271 assists in keeping the compressed gas cool at about 190K that is used in the compressed gas coolant system 270 .

[0167] The cooler 271 is also interconnected by pipework to the compressed gas coolant system 269 that is located in the VPC lower compartment 298 . The cooler 271 assists in keeping the compressed gas cool at about 220K that is used in the compressed gas coolant system 269 . The cooler 271 is also used to cool the Hydrogen gas and Hydrogen isotopes , Helium and other impurities that are trans ferred by pipework through the VPC inner wall 264 and through the VPC air gap 262 and through the VPC outer wall 260 and through the TCFRC outer wall 261 and through the TCFRC air gap 263 and through the TCFRC inner wall 265 and into the TCFRC isotope separator 259 .

[0168] The TCFRC isotope separator 259 will be remotely controlled by the MFD control computer 198 . The TCFRC isotope separator 259 will separate Hydrogen gas and Hydrogen isotopes and Helium and other impurities . Tritium separated by the TCFRC isotope separator 259 will be trans ferred by pipework to the Tritium storage system 258 and is then trans ferred by pipework to the TRC Tritium storage system 210 , as shown in Figures 5a and 5b . Deuterium separated by the TCFRC isotope separator 259 will be trans ferred by pipework to the Deuterium storage system 257 . Deuterium is trans ferred by pipework and is pumped by the Deuterium gas pump 395 from the Deuterium storage system 257 that is located within the TCFRC inner wall 265 , to the Deuterium ion source 396 , as shown in Figures 6a and 6b and 6c . Impurities separated by the TCFRC isotope separator 259 will also be trans ferred by pipework to the impurities storage system 256 , as shown in Figures 5a and 5b . Helium separated by the TCFRC isotope separator 259 will be trans ferred by pipework to the main Helium storage system 255 and is then trans ferred by pipework to the Helium cryogenic cooling plant

[0169] 201 .

[0170] Stage 10 .2 - Second inner fuel cycle systems activated .

[0171] The MFD 1 shown in Figure 3 also has a dual inner fuel cycle design feature , and one of the two inner fuel cycles is shown in the cross-sectional side view with hidden details of the MFD support and fuel inj ection sub-systems 469 of the MFD 1 , as shown in Figures 6a and 6b and 6c, and involves the secondary divertor vacuum chamber pumping pipework 24 which passes through the VPC outer wal l 460 and the VPC air gap 462 and the VPC inner wall 464 and into the VPC upper compartment The MFP and linear di f fusion pumps outer container 448 has an upper surface that has a MFP inlet 447 . Gases from the secondary divertor vacuum chamber pumping pipework 24 are pumped into the MFP inlet 447 and down into the MFP upper chamber 446 . The MFP upper chamber 446 is where Hydrogen gas and the Hydrogen isotopes are pumped and separated out and flows out of the MFP upper chamber side port 445 . The Helium and other impurities are pumped into the MFP lower chamber 441 that pumps and separates out Helium and other impurities that flows out of the MFP lower chamber side port 442 . The Hydrogen gas and Hydrogen isotopes , Helium and other impurities are then pumped into the right hand linear di f fusion pump first baf fle 440 . The first baf fle 440 needs to be kept cool at about 190K by a compressed gas coolant system 427 that is located in the VPC lower compartment 418 .

[0172] A partition floor 419 separates the VPC lower compartment 418 from the VPC upper compartment 449 .

[0173] The Hydrogen gas and Hydrogen isotopes , Helium and other impurities are then pumped downwards from the right hand linear di f fusion pump first baf fle 440 and into the right hand linear di f fusion pump second baf fle 439 . The second baf fle 439 needs to be kept cool at about 220K by a compressed gas coolant system 428 that is located in the VPC lower compartment 418 . The Hydrogen gas and Hydrogen isotopes , Helium and other impurities are then pumped downwards from the right hand linear di f fusion pump second baf fle 439 and into the right hand linear di f fusion pump main chamber 438 . Below the main chamber 438 is the right hand linear di f fusion pump wall cooling system 437 . The cooling system 437 needs to be kept cool at about 280K by a cooling water system 433 that is located in the VPC lower compartment 418 . Below the right hand linear di f fusion pump wall cooling system 437 is the right hand linear di f fusion pump Mercury boiler 436 . The Mercury boiler 436 needs to be kept hot at about 450K by a compressed gas heating system 429 that is located in the VPC lower compartment 418 . The Hydrogen gas and Hydrogen isotopes , Helium and other impurities are then trans ferred by pipework from the right hand linear di f fusion pump main chamber 438 to the right hand liquid ring pump main chamber 451 . The ring pump main chamber 451 needs to be kept cool by a Mercury cooler system 450 . The Mercury cooler system 450 needs to be kept cool at about 280K by a cooling water system 433 that is located in the VPC lower compartment 418 .

[0174] The Hydrogen gas and Hydrogen isotopes , Helium and other impurities are then trans ferred by pipework from the right hand liquid ring pump main chamber 451 to the right hand liquid ring pump gas cooler 452 . The cooler 452 is interconnected by pipework to the cooling water system 433 that is located in the VPC lower compartment 418 . The cooler 452 assists in keeping the water cool at about 280K that is used in the cooling water system 433 . The cooler 452 is interconnected by pipework to the compressed gas coolant system 434 that is located in the VPC lower compartment 418 . The cooler 452 assists in keeping the compressed gas cool at about 190K that is used in the compressed gas coolant system

[0175] 434 . The right hand liquid ring pump gas cooler 452 is also interconnected by pipework to the compressed gas coolant system 435 that is located in the VPC lower compartment 418 . The cooler 452 assists in keeping the compressed gas cool at about 220K that is used in the compressed gas coolant system

[0176] 435 . The right hand liquid ring pump gas cooler 452 is also used to cool the Hydrogen gas and Hydrogen isotopes , Helium and other impurities that are trans ferred by pipework through the VPC inner wall 464 and through the VPC air gap 462 and through the VPC outer wall 460 and through the TCFRC outer wall 461 and through the TCFRC air gap 463 and through the TCFRC inner wall 465 and into the TCFRC isotope separator 453 .

[0177] The TCFRC isotope separator 453 will be remotely controlled by the MFD control system 198 . The TCFRC isotope separator 453 will separate Hydrogen gas and Hydrogen isotopes and Helium and other impurities . Tritium separated by the TCFRC isotope separator 453 will be trans ferred by pipework to the Tritium storage system 454 and is then trans ferred by pipework to the TRC Tritium storage system 371 , as shown in Figures 6a and 6b and 6c . Deuterium separated by the TCFRC isotope separator 453 will be trans ferred by pipework to the Deuterium storage system 455 . Deuterium gas is trans ferred by pipework and pumped by the Deuterium gas pump 395 from the Deuterium storage system 455 that is located within the TCFRC inner wall 465 , to the Deuterium ion source 396 . Impurities separated by the TCFRC isotope separator 453 will be trans ferred by pipework to the impurities storage system 456 , as shown in Figures 6a and 6b and 6c . Helium separated by the TCFRC isotope separator 453 will be trans ferred by pipework to the main Helium storage system 457 and is then trans ferred by pipework to the Helium cryogenic cooling system 373 .

[0178] Stage 11 - Superconducting electromagnet feeders activated .

[0179] The electromagnet feeders 138 , 139 , 140 , and 171 , 172 , 173 , need to be powered and made operational , are designed to trans fer high electrical power, supercritical Helium coolant and low pressure vacuum pumping to the large internal stationary pressurised Helium-cooled 17Li- 83Pb liquid metal breeder blanket-encapsulated superconducting electromagnetic field coils 123 , 147 and the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 , whilst monitoring and controlling the pressure , temperature , flow and voltage drop through all sub- systems of the stationary field coils 123 , 147 and the moveable field coil 135 .

[0180] The electromagnet feeder 171 connects the cryogenic coolant and power supply lower outlet pipework 169 and the stationary field coil 123 to their auxiliary power units 195 , 249 or an external power supply, not shown in Figure 3 . The electromagnet feeder 138 connects the cryogenic coolant and power supply upper inlet pipework 132 and the stationary field coil 123 to their auxiliary power units 195 , 249 or an external power supply, not shown in Figure 3 . The electromagnet feeder 173 connects the cryogenic coolant and power supply lower outlet pipework 177 and the stationary field coil 147 to their auxiliary power units 355 , 375 or an external power supply, not shown in Figure 3 . The electromagnet feeder 140 connects the cryogenic coolant and power supply upper inlet pipework 144 and the stationary field coil 147 to their auxiliary power units 355 , 375 or an external power supply, not shown in Figure 3 . The electromagnet feeder 172 connects the cryogenic coolant and power supply lower outlet pipework 136 and the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 to their auxiliary power units 195 , 249 or an external power supply, not shown in Figure 3 . The electromagnet feeder 139 connects the cryogenic coolant and power supply upper inlet pipework 137 and the moveable field coil 135 to their auxiliary power units 195 , 249 or an external power supply, not shown in Figure 3 . Stage 12 - Twelve electromagnets , forced water or oil cooling systems energised .

[0181] The twelve external moveable actively cooled electromagnetic field coils need to be powered and made operational by powering the primary divertor end external moveable actively cooled sweeping electromagnetic field coil 108 , the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 114 , the small external moveable actively cooled electromagnetic field coils 116 , 118 , 120 , 128 , 146 , 154 , 156 , and 158 , the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 , and the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil 112 . All twelve of the external moveable actively cooled electromagnetic field coils will need to be actively cooled by a water or oil coolant system and pumps , not shown in Figure 3 .

[0182] Stage 13. 1 - Large external superconducting electromagnet energised .

[0183] When the linear actuators 133 , 170 are powered and controlled by the MFD control computer 198 , as shown in Figures 4a and 4b and 4c, the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 can be driven backwards and forwards at variable frequency and variable distance along the MFD reactor outer casing 64 .

[0184] The very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 needs to be cooled to cryogenic temperatures of approximately 4 . 5K which requires vacuum conditions around it for thermal vacuum insulation reasons . Vacuum chamber walls 134 surround the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 , and vacuum pipework to the metal foil pump inlets 447 , 291 , respectively, creates the vacuum conditions inside the vacuum chamber walls 134 , respectively .

[0185] The cryogenic coolant and power supply upper inlet pipework 137 of the field coil 135 is connected to a electromagnet feeder 139 that regulates and conveys cryogenic Helium liquid from the Helium cryogenic cooling plant pump 200 to cool and control the temperature of the field coil 135 . The electromagnet feeder 139 also connects the cryogenic coolant and power supply upper inlet pipework 137 and the field coil

[0186] 135 to their auxiliary power units 195 , 249 or an external power supply, not shown in Figures 4a and 4b and 4c . High temperature superconductor current cabling, not shown in Figures 4a and 4b and 4c, transmits the high-power currents from the auxiliary power units 195 , 249 or an external power supply, not shown in Figures 4a and 4b and 4c, to the electromagnet feeder 139 . The high-power currents are then trans ferred by the electromagnet feeder 139 to the cryogenic coolant and power supply upper inlet pipework 137 and to the field coil 135 .

[0187] The cryogenic coolant and power supply lower outlet pipework

[0188] 136 of the field coil 135 is connected to a electromagnet feeder 172 that regulates and conveys away cryogenic Helium liquid to the Helium cryogenic cooling plant pump 253 that has been heated by the field coil 135 . The electromagnet feeder 172 also connects the cryogenic coolant and power supply lower outlet pipework 136 and the field coil 135 to their auxiliary power units 195 , 249 or an external power supply, not shown in Figures 4a and 4b and 4c . High temperature superconductor current cabling, not shown in Figures 4a and 4b and 4c, transmits the high-power currents from the field coil 135 with minimum heat loading and to the cryogenic coolant and power supply lower outlet pipework 136 . The cryogenic coolant and power supply lower outlet pipework 136 then trans fers the high-power currents to the electromagnet feeder 172 . High temperature superconductor current cabling, not shown in Figures 4a and 4b and 4c, transmits the high power currents from the electromagnet feeder 172 to the room temperature auxiliary power units 195 , 249 or an external power supply, not shown in Figures 4a and 4b and 4c .

[0189] Stage 13.2 - First large internal superconducting magnetic field coil energised .

[0190] Attached releasably and securely to the lower end of the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil support upper arm 129 and to the upper end of the support lower arm 166 is the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil 123 that is required to generate the magnetic field strength of several Teslas necessary for the magnetic confinement of plasma within the MFD reactor 467 of the MFD 1 , as shown in Figures 4a and 4b and 4c . The field coil 123 could be manufactured from Niobium-Tin (Nb3Sn) or Niobium-Titanium (Nb-Ti ) and the field coil 123 becomes superconducting when cooled with supercritical Helium in the range o f 4 . 5 Kelvin ( -268 . 5 ° C ) .

[0191] The cryogenic coolant and power supply upper inlet pipework 132 of the support upper arm 129 is connected to a electromagnet feeder 138 that regulates and conveys cryogenic Helium liquid from the Helium cryogenic cooling plant pump 199 to cool and control the temperature of the field coil 123 . The electromagnet feeder 138 also connects the cryogenic coolant and power supply upper inlet pipework 132 and the field coil 123 to their auxiliary power units 195 , 249 or an external power supply not shown in Figure 3 . High temperature superconductor current cabling, not shown in Figure 3 , transmit the high-power currents from the auxiliary power units 195 , 249 or an external power supply, not shown in Figure 3 , to the electromagnet feeder 138 . The high-power currents are then trans ferred by the electromagnet feeder 138 to the cryogenic coolant and power supply upper inlet pipework 132 and to the field coil 123 with minimum heat loading .

[0192] The cryogenic coolant and power supply lower outlet pipework 169 of the support lower arm 166 is connected to a electromagnet feeder 171 that regulates and conveys away cryogenic Helium liquid to the Helium cryogenic cooling plant pump 252 that has been heated by the field coil 123 . The electromagnet feeder 171 also connects the cryogenic coolant and power supply lower outlet pipework 169 and the field coil 123 to their auxiliary power units 195 , 249 or an external power supply not shown in Figure 3 . High temperature superconductor current cabling not shown in Figures 4a and 4b and 4c, transmits the high-power currents from the field coil 123 with minimum heat loading and to the cryogenic coolant and power supply lower outlet pipework 169 . The cryogenic coolant and power supply lower outlet pipework 169 then trans fers the high-power currents to the electromagnet feeder 171 . High temperature superconductor current cabling not shown in Figure 3 , transmits the high power currents from the electromagnet feeder 171 to the room temperature auxiliary power units 195 , 249 or an external power supply, not shown in Figure 3 . First internal superconducting electromagnet Helium coolant systems activated .

[0193] The large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil 123 is surrounded by a toroidal superconducting electromagnetic field coil outer casing 126 . Mounted equidistantly between the outer casing 126 are three concentric toroidal layers of Helium cooling tubes 124 . The three layers of tubes 124 are designed to act as a Helium heat exchanger and are designed to maximise heat exchange within the three LMLi-Pb Tritium breeding blanket toroidal layers 125 .

[0194] First internal superconducting electromagnet 17Li-83Pb breeder blanket systems activated .

[0195] The breeder blanket pure LMLi-Pb upper pump 87 pumps LMLi-Pb that has had Tritium, Helium and other impurities removed, into the LMLi-Pb trans fer lower inlet pipework 167 of the support lower arm 166 .

[0196] The LMLi-Pb trans fer lower inlet pipework 167 interconnects with the three LMLi-Pb Tritium breeding blanket toroidal layers 125 , so that the LMLi-Pb flows from the LMLi-Pb trans fer lower inlet pipework 167 , and into the interconnecting three LMLi-Pb Tritium breeding blanket toroidal layers 125 .

[0197] The LMLi-Pb then travels upwards and around and through the three LMLi-Pb Tritium breeding blanket toroidal layers 125 , and trans fers its heat energy to the cooled Helium coolant that travels through three layers of tubes 124 , . The cooled LMLi-Pb in the three LMLi-Pb Tritium breeding blanket toroidal layers 125 eventually reaches the LMLi-Pb trans fer upper outlet pipework 130 , of the support upper arm 129 . The cooled LMLi-Pb is then trans ferred by pipework to the breeder blanket impure LMLi-Pb upper pump 86 , as shown in Figures 4a and 4b and 4c . The cooled impure LMLi-Pb that has passed through the three LMLi-Pb Tritium breeding blanket toroidal layers 125 and is pumped from the breeder blanket impure LMLi-Pb upper pump 86 , will have Tritium and Helium and other impurities in it that have been produced from the neutron bombardment of the cooled LMLi-Pb in the three LMLi-Pb Tritium breeding blanket toroidal layers 125 .

[0198] The breeder blanket cool Helium coolant lower pump 77 pumps cooled Helium coolant that has had Tritium and other impurities removed into the Helium trans fer upper inlet pipework 131 , of the support upper arm 129 . The Helium trans fer upper inlet pipework 131 interconnects with the three layers of tubes 124 so that the cooled Helium coolant that has had Tritium and other impurities removed flows from the Helium trans fer upper inlet pipework 131 and into the three layers of tubes 124 . The cooled Helium coolant then absorbs heat energy from the three LMLi-Pb Tritium breeding blanket toroidal layers 125 as the cooled Helium coolant travels through the three layers of tubes 124 and downwards and around and eventually reaches the Helium trans fer lower outlet pipework 168 , of the support lower arm 166 . The Helium trans fer lower outlet pipework 168 interconnects with the three layers of tubes 124 , so that the heated Helium coolant that now has Tritium and other impurities in it flows from the three layers of tubes 124 , and into the Helium trans fer lower outlet pipework 168 . The heated Helium coolant in the Helium trans fer lower outlet pipework 168 , which will also now have Tritium and other impurities in it , is trans ferred by pipework to the breeder blanket heated Helium coolant lower pump 76 , as shown in Figures 4a and 4b and 4c . Stage 13.3 - Second large internal stationary superconducting electromagnetic field coil energised .

[0199] Attached releasably and securely to the lower end of the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil support upper arm 141 , and to the upper end of the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil support lower arm 174 is the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil 147 that is required to generate the magnetic field strength of several Teslas necessary for the magnetic confinement of plasma within the MFD reactor 467 of the MFD 1 , as shown in Figures 4a and 4b and 4c .

[0200] The cryogenic coolant and power supply upper inlet pipework 144 of the support upper arm 141 is connected to a electromagnet feeder 140 that regulates and conveys cryogenic Helium liquid from the Helium cryogenic cooling plant pump 354 to cool and control the temperature of the field coil 147 . The electromagnet feeder 140 also connects the cryogenic coolant and power supply upper inlet pipework 144 and the field coil 147 to their auxiliary power units 355 , 375 or an external power supply, not shown in Figures 4a and 4b and 4c . High temperature superconductor current cabling, not shown in Figures 4a and 4b and 4c, transmit the high-power currents from the auxiliary power units 355 , 375 or an external power supply, not shown in Figures 4a and 4b and 4c, to the electromagnet feeder 140 . The high-power currents are then trans ferred by the electromagnet feeder 140 to the cryogenic coolant and power supply upper inlet pipework 144 and to the field coil 147 with minimum heat loading . The cryogenic coolant and power supply lower outlet pipework 177 of the support lower arm 174 is connected to a electromagnet feeder 173 that regulates and conveys away cryogenic Helium liquid to the Helium cryogenic cooling plant pump 374 that has been heated by the field coil 147 . The electromagnet feeder 173 also connects the cryogenic coolant and power supply lower outlet pipework 177 and the field coil 147 to their auxiliary power units 355 , 375 or an external power supply, not shown in Figures 4a and 4b and 4c . High temperature superconductor current cabling, not shown in Figures 4a and 4b and 4c, transmit the high-power currents from the field coil 147 with minimum heat loading and to the cryogenic coolant and power supply lower outlet pipework 177 . The cryogenic coolant and power supply lower outlet pipework 177 then trans fers the high-power currents to the electromagnet feeder 173 . High temperature superconductor current cabling, not shown in Figures 4a and 4b and 4c, transmits the high-power currents from the electromagnet feeder 173 to the room temperature auxiliary power units 355 , 375 or an external power supply, not shown in Figures 4a and 4b and 4c .

[0201] Second internal superconducting electromagnet Helium coolant systems activated .

[0202] The field coil 147 is surrounded by a toroidal superconducting electromagnetic field coil outer casing 150 . Mounted equidistantly between the field coil 147 and the toroidal superconducting electromagnetic field coil outer casing 150 are three concentric toroidal layers of Helium cooling tubes 148 . The three layers of tubes 148 are designed to act as a Helium heat exchanger and are designed to maximise heat exchange within the three LMLi-Pb Tritium breeding blanket toroidal layers 149 . Second internal superconducting electromagnet 17Li-83Pb breeder blanket systems activated .

[0203] The breeder blanket pure LMLi-Pb lower pump 98 pumps LMLi-Pb that has had Tritium, Helium and other impurities removed, into the LMLi-Pb trans fer lower inlet pipework 175 of the support lower arm 174 .

[0204] The LMLi-Pb trans fer lower inlet pipework 175 interconnects with the three LMLi-Pb Tritium breeding blanket toroidal layers 149 so that the LMLi-Pb flows from the LMLi-Pb trans fer lower inlet pipework 175 and into the interconnecting three LMLi-Pb Tritium breeding blanket toroidal layers 149 .

[0205] The LMLi-Pb then travels upward and around and through the three LMLi-Pb Tritium breeding blanket toroidal layers 149 and trans fers its heat energy to the cooled Helium coolant that travels through three layers of tubes 148 . The cooled LMLi-Pb in the three LMLi-Pb Tritium breeding blanket toroidal layers 149 eventually reaches the LMLi-Pb trans fer upper outlet pipework 142 of the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coil support upper arm 141 . The cooled LMLi-Pb is then trans ferred by pipework to the breeder blanket impure LMLi-Pb lower pump 99 , as shown in Figures 4a and 4b and 4c . The cooled impure LMLi-Pb that has passed through the three LMLi-Pb Tritium breeding blanket toroidal layers 149 and is pumped from the breeder blanket impure LMLi-Pb lower pump 99, will have Tritium and Helium and other impurities in it that have been produced from the neutron bombardment of the cooled LMLi-Pb in the three LMLi-Pb Tritium breeding blanket toroidal layers 149 .

[0206] The breeder blanket cool Helium coolant upper pump 68 pumps cooled Helium coolant that has had Tritium and other impurities removed, into the Helium trans fer upper inlet pipework 143 of the support upper arm 141 . The Helium trans fer upper inlet pipework 143 interconnects with the three layers of tubes 148 so that the cooled Helium coolant that has had Tritium and other impurities removed flows from the Helium trans fer upper inlet pipework 143 and into the three layers of tubes 148 . The cooled Helium coolant then absorbs heat energy from the three LMLi-Pb Tritium breeding blanket toroidal layers 149 as the cooled Helium coolant travels through the three layers of tubes 148 and downward and around and eventually reaches the Helium trans fer lower outlet pipework 176 of the support lower arm 174 . The Helium trans fer lower outlet pipework 176 interconnects with the three layers of tubes 148 so that the heated Helium coolant that now has Tritium and other impurities in it , flows from the three layers of tubes 148 and into the Helium trans fer lower outlet pipework 176 . The heated Helium coolant in the Helium trans fer lower outlet pipework 176 which will also now have Tritium and other impurities in it , is then trans ferred by pipework to the breeder blanket heated Helium coolant upper pump 69 , as shown in Figures 4a and 4b and 4c .

[0207] Stage 14 - Plasma heating method 1 : I . C . R. H . systems energised .

[0208] Seven di f ferent plasma heating methods are used to heat the Deuterium and Tritium gas and pellets fuel that has been inj ected into the MFD reactor 467 of the mobile fusion device 1 to the temperatures required to produce fusion reactive Deuterium and Tritium plasma . The seven plasma heating methods are : ion cyclotron resonance heating ICRH, electron cyclotron resonance heating ECRH,

[0209] Deuterium neutral beam inj ection heating DNBIH, • Tritium neutral beam inj ection heating TNBIH,

[0210] • magnetic field current variation heating,

[0211] • magnetic field movement variation heating, and

[0212] • alpha channelling ef fect heating .

[0213] The first plasma heating method is the ion cyclotron resonance heating systems whose ICRH radio frequency generators and high power supplies and cooling systems and transmission lines , not shown in Figures 4a and 4b and 4 c, are powered to generate and transmit high power radio frequency waves with a variable frequency of approximately 40 MHz to 55 MHz . These are trans ferred along the transmission lines to the four ion cyclotron resonance heating systems 3 , 4 , 5 , 6 that each have ion cyclotron resonance heating launching system antennas and limiters , that emit high intensity beams of ion cyclotron resonance electromagnetic radiation 188 , 189 and 190 , 191 respectively, that converge on the left central plasma region 193 and converge on the right central plasma region 194 , respectively, whose energy is trans ferred to the ions in the plasma, so heating the plasma in the MFD reactor 467 , as shown in Figures 4a and 4b and 4c .

[0214] The 14 . 1MeV fusion neutrons produced by the fusion reactions within the MFD reactor 467 can also travel through the four ion cyclotron resonance heating systems 3 , 4 , 5 , 6 and are captured and thermali zed in the LMLi-Pb Tritium breeding blankets , where the neutron kinetic energy is trans formed into heat energy and collected by the Helium coolant flowing in the double walls of the double-walled 17Li- 83Pb Tritium breeding boxes , not shown in Figures 4a and 4b and 4c, that are securely and releasably located on the ends of the ion cyclotron resonance heating systems 3 , 4 , 5 , 6 shown in

[0215] Figures 4a and 4b and 4c . Stage 15 Plasma heating method 2: E.C.R.H. systems energised.

[0216] The second plasma heating method is the electron cyclotron resonance heating systems whose powerful gyrotrons and high power supplies and cooling systems and transmission lines, not shown in Figures 4a and 4b and 4c, are powered to generate and transmit high power radio frequency waves which are transferred along transmission lines to electron cyclotron resonance heating directable launchers 121, 122, and 151, 152.

[0217] The directable launchers 121, 122, and 151, 152, are designed to heat electrons in the plasma with directable high intensity beams of electron cyclotron resonance electromagnetic radiation 184, 185 and 186, 187 respectively, at a frequency of approximately 170GHz which is the resonant frequency of electrons. The higher energy electrons in the plasma are then able to transfer their energy to the ions in the plasma through electron and ion collisions within the MFD reactor 467.

[0218] The directable radiation beams 184, 185 and 186, 187 can be made to transmit to and converge on the central plasma region 192 or on any part of the plasma within the MFD reactor 467 by the directable launchers 121, 122, and 151, 152, respectively.

[0219] The directable radiation beams 184, 185, and 186, 187, can be transmitted through air which simplifies the design of the electron cyclotron resonance heating system and allows the directable launchers 121, 122, and 151, 152, respectively, to be releasably and securely attached to the outside of the MFD reactor outer casing 64, so simplifying maintenance. Stage 16 - Four divertor neutral gas injection systems activated .

[0220] The neutral gas inj ection primary divertor systems can now be made operational by powering the primary divertor impurity seeding neutral gas containers 27 , 28 that pumps impurity seeding neutral gas , such as Argon, Neon, Krypton, Xenon through the primary divertor impurity seeding neutral gas pipes 25 , 26 , respectively, and into the primary divertor .

[0221] The neutral gas inj ection secondary divertor systems can now be made operational by powering the secondary divertor impurity seeding neutral gas containers 51 , 52 that pumps impurity seeding neutral gas , such as Argon, Neon, Krypton, Xenon through the secondary divertor impurity seeding neutral gas pipes 43 , 44 , respectively, and into the secondary divertor .

[0222] Stage 17 - Deuterium and Tritium fuel pellet injection systems activated .

[0223] The fuel pellet inj ection system can now be powered and made operational by trans ferring Tritium by pipework that is pumped by the Deuterium and Tritium fuel storage and pellet manufacturing container Tritium pump 391 from the TRC Tritium delivery system 372 and into the Deuterium and Tritium fuel storage and pellet manufacturing container cooler 393 , where the Tritium is frozen and is then trans ferred to the interconnected Deuterium and Tritium fuel storage and pellet manufacturing container extruder 388 that punches out millimeter-si zed frozen Tritium pellets 381 . The Deuterium and Tritium fuel storage and pellet manufacturing container gas gun 385 is then used to propel the millimeter- si zed frozen Tritium pellets 381 at high speeds of up to several thousand km / h along the gas gun barrel 380 and out through the Deuterium and Tritium fuel storage and pellet manufacturing container ori fice 378 and through the inj ection tube 55 . The frozen Tritium pellets 381 should be able to penetrate deep into the fusion plasma before being ionised .

[0224] Deuterium is also simultaneously trans ferred by pipework and is pumped by the Deuterium and Tritium fuel storage and pellet manufacturing container Deuterium pump 392 from the Deuterium storage system 455 and into the Deuterium and Tritium fuel storage and pellet manufacturing container cooler 393 , where the Deuterium is frozen and is then trans ferred to the interconnected Deuterium and Tritium fuel storage and pellet manufacturing container extruder 388 that punches out millimeter-si zed frozen Deuterium pellets 382 . The gas gun 385 is then used to propel the millimeter-si zed frozen Deuterium pellets 382 along the gas gun barrel 380 and out through the Deuterium and Tritium fuel storage and pellet manufacturing container ori fice 378 and through the inj ection tube 55 . The Deuterium pellets 382 should be able to penetrate deep into the fusion plasma before being ionised .

[0225] The 14 . 1MeV fusion neutrons produced by the fusion reactions within the MFD reactor 467 can also travel up the inj ection tube 55 and through the Deuterium and Tritium fuel storage and pellet manufacturing container ori fice 378 and into the Deuterium and Tritium fuel storage and pellet manufacturing container 379 , and are captured and thermali zed in the LMLi-Pb Tritium breeding blanket 405 where the neutron kinetic energy is trans formed into heat energy and collected by the Helium coolant flowing in the double walls of the double-walled 17Li- 83Pb Tritium breeding box 404 . The breeder blanket pure LMLi-Pb lower pump 98 pumps LMLi-Pb that has had Tritium, Helium and other impurities removed, into the LMLi-Pb inlet 406 of the LMLi-Pb Tritium breeding blanket 405 .

[0226] The cooled LMLi-Pb that exits the LMLi-Pb outlet 407 of the LMLi-Pb Tritium breeding blanket 405 will have Tritium and other impurities in it , is then trans ferred by pipework by the breeder blanket impure LMLi-Pb lower pump 99 to the 17Li- 83Pb Helium separator 341 .

[0227] The breeder blanket cool Helium coolant upper pump 68 pumps cooled Helium coolant that has had Tritium and other impurities removed, into the cold Helium inlet 409 of the double-walled 17Li- 83Pb Tritium breeding box 404 .

[0228] The heated Helium coolant that exits the heated Helium outlet 410 of the double-walled 17Li- 83Pb Tritium breeding box 404 will have Tritium and other impurities in it , is then trans ferred by pipework by the breeder blanket heated Helium coolant upper pump 69 to the Helium Tritium separator 335 , as shown in Figures 6a and 6b and 6c .

[0229] Stage 18 Plasma heating method 3 : D . N . B . I . H . systems energised .

[0230] The third plasma heating method is the Deuterium neutral beam inj ection heating system that can be made operational by trans ferring Deuterium gas by pipework and pumped by the Deuterium gas pump 395 from the Deuterium storage system 455 that is located within the Tritium cleanup and fuel recovery container inner wall 465 , to the Deuterium ion source 396 . The Deuterium ion source 396 ionises the Deuterium gas and Deuterium ion acceleration grids 390 accelerate the Deuterium ions along the Deuterium neutraliser tube 389 . The Deuterium neutrali zer tube 389 contains Deuterium gas at high pressure that neutrali zes the accelerated Deuterium ions within the Deuterium neutrali zer tube 389 . Lower energy but still charged Deuterium ions will be deflected by the electric field created by the ion dump electric field coil 387 into an ion dump 386 . A Deuterium neutral beam calorimeter 384 is releasably and securely attached to the upper inside surface of the Deuterium neutral beam inj ection heating container 383 . The interior of the Deuterium neutral beam inj ection heating container 383 needs to be kept at a very low pressure , so the Deuterium neutral beam inj ection heating vacuum pumping port 394 is interconnected using vacuum pipework to the metal foil di f fusion pump inlet 447 . High velocity Deuterium neutral particles will then be shot out of the end of the Deuterium neutrali zer tube 389 and the Deuterium neutral beam inj ection heating tube 53 and will be able to penetrate into the plasma within the MFD reactor 467 and will have traj ectory paths directed at the Deuterium and Tritium neutral particles traj ectories convergence point 183 which is the centre of the central plasma region 192 where , through rapid collisions , the high velocity Deuterium neutral particles will become ionised by the high temperature plasma and will trans fer their energy to the plasma ions and plasma electrons within the MFD reactor 467 .

[0231] The 14 . 1MeV fusion neutrons produced by fusion reactions within the MFD reactor 467 are able to travel up the Deuterium neutral beam inj ection heating tube 53 , and are captured and thermali zed in the LMLi-Pb Tritium breeding blanket 400 , where the neutron kinetic energy is trans formed into heat energy and collected by the Helium coolant flowing in the double-walled 17Li- 83Pb Tritium breeding box 397 . The breeder blanket pure LMLi-Pb lower pump 98 pumps LMLi-Pb that has had Tritium, Helium and other impurities removed, into the LMLi-Pb inlet 398 of the LMLi-Pb Tritium breeding blanket 400 .

[0232] The cooled LMLi-Pb that exits the LMLi-Pb outlet 399 of the LMLi-Pb Tritium breeding blanket 400 will have Tritium and other impurities in it , is then trans ferred by pipework by the breeder blanket impure LMLi-Pb lower pump 99 to the 17Li- 83Pb Helium separator 341 .

[0233] The breeder blanket cool Helium coolant upper pump 68 pumps cooled Helium coolant that has had Tritium and other impurities removed, into the cold Helium inlet 402 of the double-walled 17Li- 83Pb Tritium breeding box 397 .

[0234] The heated Helium coolant that exits the heated Helium outlet 401 will have Tritium and other impurities in it , are then trans ferred by pipework by the breeder blanket heated Helium coolant upper pump 69 to the Helium Tritium separator 335 , as shown in Figures 6a and 6b and 6c .

[0235] Stage 19 - Plasma heating method 4 : T . N . B . I . H . systems energised .

[0236] The fourth plasma heating method is the Tritium neutral beam inj ection heating system that can be made operational by trans ferring Tritium gas by pipework and pumped by the Tritium gas pump 317 from the Tritium delivery system 372 that is located within the TRC inner wall 360 , to the Tritium ion source 316 . The Tritium ion source 316 ionises the Tritium gas and Tritium ion acceleration grids 314 accelerate the Tritium ions along the Tritium neutraliser tube 313 . The Tritium neutrali zer tube 313 contains Tritium gas at high pressure that neutrali zes the accelerated Tritium ions within the Tritium neutrali zer tube 313 . Lower energy but still charged Tritium ions will be deflected by the electric field created by the ion dump electric field coil 312 into an ion dump 311 . A Tritium neutral beam calorimeter 310 is releasably and securely attached to the upper inside surface of the Tritium neutral beam inj ection heating container 309 . The interior of the Tritium neutral beam inj ection heating container 309 needs to be kept at a very low pressure , so the Tritium neutral beam inj ection heating vacuum pumping port 315 is interconnected using vacuum pipework to the metal foil di f fusion pump inlet 447 . High velocity Tritium neutral particles will then be shot out of the end of the Tritium neutrali zer tube 313 and the Tritium neutral beam inj ection heating tube 54 and will be able to penetrate into the plasma within the MFD reactor 467 and will have traj ectory paths directed at the Deuterium and Tritium neutral particles traj ectories convergence point 183 (which is the centre of the central plasma region 192 ) where , through rapid collisions , the high velocity Tritium neutral particles will become ionised by the high temperature plasma and will trans fer their energy to the plasma ions and plasma electrons within the MFD reactor 467 .

[0237] The 14 . 1MeV fusion neutrons produced by fusion reactions within the MFD reactor 467 are able to travel up the Tritium neutral beam inj ection heating tube 54 , and are captured and thermali zed in the LMLi-Pb Tritium breeding blanket 319 , where the neutron kinetic energy is trans formed into heat energy and collected by the Helium coolant flowing in the double walls of the double-walled 17Li- 83Pb Tritium breeding box 318 .

[0238] The breeder blanket pure LMLi-Pb lower pump 98 pumps LMLi-Pb that has had Tritium, Helium and other impurities removed, into the LMLi-Pb inlet 320 of the LMLi-Pb Tritium breeding blanket 319 . The cooled LMLi-Pb that exits the LMLi-Pb outlet 321 of the LMLi-Pb Tritium breeding blanket 319 will have Tritium and other impurities in it , is then trans ferred by pipework by the breeder blanket impure LMLi-Pb lower pump 99 to the 17Li- 83Pb Helium separator 341 .

[0239] The breeder blanket cool Helium coolant upper pump 68 pumps cooled Helium coolant that has had Tritium and other impurities removed, into the cold Helium inlet 323 of the double-walled 17Li- 83Pb Tritium breeding box 318 .

[0240] The heated Helium coolant that exits the heated Helium outlet 322 will have Tritium and other impurities in it , are then trans ferred by pipework by the breeder blanket heated Helium coolant upper pump 69 to the Helium Tritium separator 335 , as shown in Figures 6a and 6b and 6c .

[0241] Stage 20 - Plasma heating method 5 : Electromagnetic field coils current variation .

[0242] In order to heat the plasma to the temperatures , densities and energy confinement times required to initiate fusion between Deuterium and Tritium, magnetic field variation plasma compression heating is used as the fi fth plasma heating method, which relies upon magnetic field variation through the variation of current in the primary divertor end external moveable actively cooled sweeping electromagnetic field coil 108 , the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 114 , the small external moveable actively cooled electromagnetic field coils 116 , 118 , 120 , 128 , 146 , 154 , 156 , 158 , the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 , the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil 112 , the large internal stationary pressurised Helium cooled 17Li-83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coils 123, 147, and the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135.

[0243] Stage 21 - Plasma heating method 6: Electromagnetic field coil linear actuation.

[0244] A magnetically confined plasma should start to be formed within the MFD reactor 467 and the magnetically formed plasma needs to be heated further using the sixth plasma heating method which is electromagnetic field coil linear actuation plasma compression heating which relies upon longitudinally oscillating the external moveable electromagnetic field coils.

[0245] • The linear actuators 106, 107 are releasably and securely and internally mounted within the primary divertor end outer collar 105. The linear actuators 110, 111 are releasably and securely and internally mounted within the secondary divertor end outer collar 109. When the linear actuators 106, 107, and 113, 161, and 115, 162, and 117, 163, and 119, 164, and 127, 165, and 133, 170, and 145, 178, and 153, 179, and 155, 180, and 157, 181, and 159, 182, and 110, 111, that could be pneumatic or hydraulic pistons or electro-mechanical linear actuators, are powered, the following can be driven backwards and forwards at variable frequency and variable distance:

[0246] • the primary divertor end external moveable actively cooled sweeping electromagnetic field coil 108,

[0247] • the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 114, • the small external moveable actively cooled electromagnetic field coil 116 ,

[0248] • the small external moveable actively cooled electromagnetic field coil 118 ,

[0249] • the small external moveable actively cooled electromagnetic field coil 120 ,

[0250] • the small external moveable actively cooled electromagnetic field coil 128 ,

[0251] • the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 ,

[0252] • the small external moveable actively cooled electromagnetic field coil 146 ,

[0253] • the small external moveable actively cooled electromagnetic field coil 154 ,

[0254] • the small external moveable actively cooled electromagnetic field coil 156 ,

[0255] • the small external moveable actively cooled electromagnetic field coil 158 ,

[0256] • the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 ,

[0257] • the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil 112 .

[0258] This electromagnetic field coil linear actuation plasma compression heating of the magnetically compressed central fusion plasma volume 471 and the magnetically compressed primary divertor end fusion plasma volume 472 and the magnetically compressed secondary divertor end fusion plasma volume 473 can be controlled by the MFD control computer 198 and can be performed continually in a cyclical manner for steady state operations or in the initial start-up phase to assist with the initiation of plasma fusion conditions within the MFD reactor 467 , whilst simultaneously minimising the MFD 1 start-up power requirements from the auxiliary power units 195 , 249 , 355 , 375 .

[0259] Stage 22 - Plasma heating method 7 : Alpha channelling effect plasma heating systems operational .

[0260] It would be beneficial i f the Helium nuclei known as alpha particles , that are also generated by the fusion of Deuterium and Tritium, could be contained within the MFD reactor 467 as long as possible , to trans fer as much of the 3 . 5 MeV Helium nuclei energy to the other plasma ions and plasma electrons as possible , before the neutralised Helium ash is evacuated from the MFD reactor 467 by the primary divertor and secondary divertor . Collectively, this would increase plasma fusion reactivity and would be a contributory factor to economic initiation of steady state fusion ignition .

[0261] The ion cyclotron resonance heating systems 3 , 4 , and 5 , 6 that are used initially as ion cyclotron resonance heaters , could secondly be used as alpha channelling ef fect plasma heaters . The ion cyclotron resonance heating systems 3 and 5 , for example , could be used to launch mode-converted ion Bernstein RF waves IBW ' s , and the ion cyclotron resonance heating systems 4 and 6 , for example , could be s imultaneously used to launch lower frequency RF waves .

[0262] The six plasma heating methods described previously result in the creation of the magnetically compressed central fusion plasma volume 471 and the magnetically compressed primary divertor end fusion plasma volume 472 and the magnetically compressed secondary divertor end fusion plasma volume 473 , where the electron temperature exceeds the ion temperature , because the energetic alpha particles preferentially heat electrons collisionally (by collision) . However, the MFD reactor 467 could utili ze a seventh plasma heating method called alpha-channelling ef fect plasma heating as a waveparticle manipulation technique , whereby the 3 . 5 MeV alpha particles could be slowed down collisionlessly (without collision) and the alpha particles ' energy could be trans ferred or channelled to the mode-converted ion Bernstein RF waves IBW s and lower frequency RF waves , rather than being slowed down by plasma electrons collisionally . The mode converted ion Bernstein RF waves IBW s and lower frequency RF waves would therefore channel as much of the alpha particles ' energy to energetic Deuterium ions and Tritium ions on a collisionless time scale . The energetic Deuterium ions and Tritium ions would then equilibrate with the bulk relatively lower-energy Deuterium ions and Tritium ions which would then trans fer their energy and heat the plasma electrons on a collisional timescale .

[0263] There will be a greater concentration of high-energy alphaparticles in the magnetically compressed central fusion plasma volume 471 and the magnetically compressed primary divertor end fusion plasma volume 472 and the magnetically compressed secondary divertor end fusion plasma volume 473 and there will be a higher concentration of lower-energy alpha-particles at the periphery close to the MFD reactor inner vacuum chamber 2 . The alpha particles will therefore tend to di f fuse towards the periphery through the resonant interaction with mode-converted ion Bernstein RF waves IBW s and the lower frequency RF waves , and in doing so the alpha particles will lose their energy to the RF waves .

[0264] Advantageously, the MFD reactor 467 has a Deuterium and

[0265] Tritium gas puf fing inj ection tube 56 that can inj ect Deuterium and Tritium fuel gas into the MFD reactor 467 periphery close to the MFD reactor inner vacuum chamber 2 , which means that there will be a relatively higher density of low energy Deuterium ions and Tritium ions at the periphery close to the MFD reactor inner vacuum chamber 2 ( as they will be relatively newly ioni zed after being inj ected as gas ) , and the density of higher energy Deuterium ions and Tritium ions will increase towards the magnetically compressed central fusion plasma volume 471 and the magnetically compressed primary divertor end fusion plasma volume 472 and the magnetically compressed secondary divertor end fusion plasma volume 473 , which are called the three MFD reactor fusion regions , due to their greater plasma temperatures and plasma densities . However, within the three MFD reactor fusion regions , ( that will have a certain volume governed by the Lawson criterion where high enough plasma density x high enough plasma temperature x high enough energy confinement time have all been collectively exceeded) , the density of higher energy Deuterium ions and Tritium ions should be very low as the higher energy Deuterium ions and Tritium fuel ions will have instantaneously fused by Deuterium-Tritium fusion reactions to form alpha particles (Helium-4 ) and high energy neutrons , as explained in ignition stage 25 .

[0266] Consequently, the Deuterium ions and Tritium ions will tend to di f fuse in the mode-converted ion Bernstein RF waves IBW ' s and the lower frequency RF waves towards the three MFD reactor fusion regions , and in doing so the Deuterium ions and Tritium ions will gain energy from the mode converted ion Bernstein RF waves IBW ' s and the lower frequency RF waves . It can therefore be predicted that the mode-converted ion Bernstein RF waves IBW ' s and the lower frequency RF waves that grow through ej ecting alpha particles whilst absorbing alpha particle energy, could also transport Deuterium ions and Tritium ions from the periphery close to the MFD reactor inner vacuum chamber 2 to the three MFD reactor fusion regions whilst heating them to higher energies with much higher fusion reactivity . The MFD reactor 467 would then be operating in the very beneficial hot-ion mode where plasma Deuterium ions and Tritium ions are hotter than plasma electrons , which will substantially increase the fusion reactivity within the MFD reactor 467 with potentially signi ficant steady state operational and economic benefits in building and operating the MFD 1 .

[0267] Many existing voluminous toroidal fusion reactor designs also suf fer from plasma instabilities that would be exacerbated by the energy from alpha particles that would have deleterious ef fects on their plasma confinement and could lead to increases in their reactor wall heat loading . However, with the MFD 1 operating in the advantageous hot-ion mode , the alpha particle energy is designed to be removed by alpha channelling ef fect plasma heating so removing the source of energy that would be available to power these detrimental and deleterious plasma instabilities , so potentially maximising the MFD reactor 467 steady state plasma stability .

[0268] The rapid and beneficial expulsion of the spent cold alpha particles , called polluting Helium ash, that are pumped out through the primary divertor Hel ium cooled pumping channels 18 , 29 , and out through the secondary divertor Helium cooled pumping channels 41 , 42 , from the MFD reactor 467 , and the use of the channelled alpha particle power for purposes other than plasma electron heating, could potentially have very signi ficant economic viability and steady state operational beneficial ef fects for the MFD 1 design shown in Figure 3 . Magnetic mirrors / field line topography produced and inherent MHD s tabi 1 i ty .

[0269] Figures 7a and 7b shows the cross-sectional side view with hidden details of the MFD reactor with internal magnetic field configuration 467A of the MFD 1 shown in Figure 3 .

[0270] In Tokamaks and spherical Tokamaks , magnetohydrodynamics stability is challenging even at low Beta . This is due to their complex concave and toroidal magnetic field geometry that has a magnetic field strength that decreases with radial distance from the central longitudinal axis of their fusion reactors and has externally applied magnetic field lines that are outwardly directed and have a negative outward gradient and are concave-shaped which weaken with radial distance and so are unable to counteract increasing plasma pressure with its radially weakening magnetic field pressure which confers poor magnetohydrodynamic stabili zation and B<1 .

[0271] The convoluted compact magnetic bottle , with magnetic mirror ends , magnetic field line topography within the MFD reactor 467 , as shown in Figures 7a and 7b, features axial point cusp magnetic field lines and radial ring cusp magnetic field lines whose magnetic field strength increases with radial distance from the central longitudinal axis of the MFD reactor 467 of the MFD 1 . The externally applied magnetic field lines are inward directed and have a positive outward gradient and are convex shaped which strengthen with radial distance and so is able to counteract increasing plasma pressure with its radially strengthening magnetic field pressure which should potentially confer very high magnetohydrodynamic stabili zation and B« 1 .

[0272] This suggests that as the plasma pressure from fusion reactions within the MFD reactor 467 increases and the fusion plasma attempts to expand due to its increasing plasma pressure, the internal magnetic field configuration 467A of the MFD 1 becomes stronger at the magnetically confined plasma boundary wall, so counteracting and pushing back on the fusion plasma within the MFD reactor 467, and so increasing the magnetic field confinement of the fusion plasma within the MFD reactor 467. Unlike Tokamak or Spherical Tokamak fusion reactor designs, the MFD reactor 467 of the MFD 1, therefore, potentially has an in-built self-regulating magnetic field plasma confinement feedback design feature.

[0273] The magnetically confined plasma boundary wall inside the MFD reactor with internal magnetic field configuration 467A of the MFD 1, as shown in Figure 7a and 7b, consists of a scrape-off magnetically confined plasma layer 483, 490, 476, 474, 475, 478, 479, 477, 480, 481, 487, 488, 498, 501, 494, 495, 496, 497, 504, 505, 516, 517.

[0274] The primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 114 and the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 are multifunctional and are designed to create magnetic mirrors points 499, 500, that are designed to decrease the axial point cusp plasma losses 502, 503, and 514, 515, respectively, that are produced by the field coils 123, 147, respectively, along the central longitudinal axis of the MFD reactor with internal magnetic field configuration 467A of the MFD 1.

[0275] The stable internal magnetic field configuration of the convoluted compact magnetic bottle with magnetic mirror ends magnetic field line topography within the MFD reactor 467 of the MFD 1, is designed to maintain the magnetohydrodynamic plasma stability of the fusion plasma by maintaining the strongest possible magnetically confined plasma boundary wall that magnetically confines the fusion plasma and prevents the fusion plasma from expanding within the MFD reactor 467 .

[0276] Magnetic ring cusps produced .

[0277] When the field coil 123 is controlled by the MFD control computer 198 and is supplied with electrical power from the auxiliary power units 195 , 249 , magnetic ring cusp magnetic field lines 482 , 489 , 485 , 492 will be produced on either side of the field coil 123 .

[0278] When the field coil 147 is controlled by the MFD control computer 198 and is supplied with electrical power from the auxiliary power units 355 , 375 , magnetic ring cusp magnetic field lines 484 , 491 , 486 , 493 will be produced on either side of the field coil 147 .

[0279] Magnetic ring cusps are places where two magnetic fields sharply bend and repel one another . Magnetic ring cusps are very beneficial as plasma predominantly leaks through the edges and apexes of the magnetic ring cusps which minimises the area over which plasma can be lost . Magnetic ring cusps have two main advantages . Firstly, the magnetic fields are directed and bent inwards which means that plasma confined on the magnetic field lines travels inwards to the centre of the MFD reactor 467 of the MFD 1 . Secondly, magnetic ring cusps also have null points in their centre where there is no magnetic field and which is where any fusion plasma will travel to and will accumulate in .

[0280] When the electrical power is increased to the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 and to the small external moveable actively cooled electromagnetic field coil 128 , the magnetic ring cusp magnetic field lines 482 produced by the field coil 123 are shown in Figures 7a and 7b to be re- directed towards the field coil support upper arm 129 .

[0281] When the electrical power is increased to the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 114 , and to the small external moveable actively cooled electromagnetic field coils 116 , 118 and 120 , the magnetic ring cusp magnetic field lines 485 produced by the field coil 123 are shown in Figures 7a and 7b to be re-directed towards the support upper arm 129 .

[0282] When the electrical power is increased to the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 and to the small external moveable actively cooled electromagnetic field coil 128 , the magnetic ring cusp magnetic field lines 489 produced by the field coil 123 are shown in Figures 7a and 7b to be redirected towards the support lower arm 166 .

[0283] When the electrical power is increased to the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 114 , and to the small external moveable actively cooled electromagnetic field coils 116 , 118 and 120 , the magnetic ring cusp magnetic field lines 492 produced by the field coil 123 are shown in Figures 7a and 7b to be re-directed towards the support lower arm 166 .

[0284] The magnetic ring cusp magnetic field lines 482 , 485 produced by the field coil 123 , will close and will reconnect with each other .

[0285] The magnetic ring cusp magnetic field lines 489 , 492 produced by the field coil 123 , will also close and will reconnect with each other . The only disturbance of the reconnection of the magnetic ring cusp magnetic field lines 482 , 485 produced by the field coil 123 will be the support upper arm 129 .

[0286] The only disturbance of the reconnection of the magnetic ring cusp magnetic field lines 489 , 492 produced by the field coil 123 will be the support lower arm 166 .

[0287] The closing and reconnection of the magnetic ring cusp magnetic field lines 482 , 485 and 489 , 492 , are designed to suppress the amount of open field lines and so reduce magnetic ring cusp losses through the closing and reconnection of the magnetic ring cusp magnetic field lines 482 , 485 and 489 , 492 .

[0288] When the electrical power is increased to the field coil 135 and to the field coil 146 , the magnetic ring cusp magnetic field lines 484 produced by the field coil 147 are shown in Figures 7a and 7b to be re-directed towards the support upper arm 141 .

[0289] When the electrical power is increased to the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 , and to the small external moveable actively cooled electromagnetic field coils 154 , 156 and 158 , the magnetic ring cusp magnetic field lines 486 produced by the field coil 147 are shown in Figures 7a and 7b to be re-directed towards the support upper arm 141 .

[0290] When the electrical power is increased to the field coil 135 and to the small external moveable actively cooled electromagnetic field coil 146 , the magnetic ring cusp magnetic field lines 491 produced by the field coil 147 are shown in Figures 7a and 7b to be re-directed towards the support lower arm 174 .

[0291] When the electrical power is increased to the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 , and to the small external moveable actively cooled electromagnetic field coils 154 , 156 and 158 , the magnetic ring cusp magnetic field lines 493 produced by the field coil 147 are shown in Figures 7a and 7b to be re-directed towards the support lower arm 174 .

[0292] The magnetic ring cusp magnetic field lines 482 , 485 produced by the field coil 123 , will close and will reconnect with each other .

[0293] The magnetic ring cusp magnetic field lines 489 , 492 produced by the field coil 102A, will also close and will reconnect with each other .

[0294] The only disturbance of the reconnection of the magnetic ring cusp magnetic field lines 482 , 485 produced by the field coil 123 will be the support upper arm 129 .

[0295] The only disturbance of the reconnection of the magnetic ring cusp magnetic field lines 489 , 492 produced by the field coil 123 will be the support lower arm 166 .

[0296] The closing and reconnection of the magnetic ring cusp magnetic field lines 482 , 485 and 489 , 492 , are designed to suppress the amount of open field lines and so reduce magnetic ring cusp losses from the magnetic ring cusp magnetic field lines 482 , 485 and 489 , 492 .

[0297] The magnetic ring cusp magnetic field lines 484 , 486 produced by the field coil 147 , will close and will reconnect with each other .

[0298] The magnetic ring cusp magnetic field lines 491 , 493 produced by the field coil 147 , will also close and will reconnect with each other . The only disturbance of the reconnection of the magnetic ring cusp magnetic field lines 484 , 486 produced by the field coil 147 will be the support upper arm 141 .

[0299] The only disturbance of the reconnection of the magnetic ring cusp magnetic field lines 491 , 493 produced by the field coil 147 will be the support lower arm 174 .

[0300] The closing and reconnection of the magnetic ring cusp magnetic field lines 484 , 486 and 491 , 493 , are designed to suppress the amount of open field lines and so reduce magnetic ring cusp losses from the magnetic ring cusp magnetic field lines 484 , 486 and 491 , 493 .

[0301] Stage 23 - Plasma diagnostic sensors activated .

[0302] The plasma conditions within the MFD reactor 467 of the MFD 1 need to be continuously measured in order to optimise the fusion reaction conditions . This could be accomplished by taking sensor measurements which are used by the MFD control computer 198 to control the MFD 1 sub-systems described previously, and are designed to maximi ze MFD 1 controllability, reliability and electrical output for extended periods of continuous operation . Diverse plasma sensors could be contained within the sensor container 470 , as shown in Figure 1 , and are directed along the sensor container tube , not shown in Figure 1 . The sensor container tube is in the direct line-of-path of the Deuterium and Tritium neutral particles traj ectories convergence point 183 which is the centre of the central plasma region 192 . A diverse array of non-invasive electromagnetic-based plasma diagnostic sensors could be used that rely on long wavelengths such as infrared, THz , millimetre waves and microwaves , which are more likely to operate for prolonged periods when exposed to the high radiation and high neutron flux and high temperatures produced by the fusion of Deuterium and Tritium within the MFD reactor 467 , compared to invasive probe-like and optical-based plasma diagnostics , whi lst also minimi z ing the number of diagnostics access ports in the MFD reactor inner vacuum chamber 2 and associated costs . Microwave ref lectometry and polarimetry using multiple wide area coverage and electronically steerable microwave antennae attached at various locations to the MFD reactor inner vacuum chamber 2 , and direct line-of-sight laser-based interferometry and polarimetry, micro-channel plate photomultiplier neutron detectors , scintillator gamma ray detectors , x-ray to infra-red spectroscopy and bolometers contained within the sensor container 470 , could all be used as a suite of modular and upgradeable and highly survivable plasma diagnostic sensors , not shown in Figures 6a and 6b and 6c .

[0303] The sensor container 470 is shown in Figure 1 but is not shown in Figures 6a and 6b and 6c because the sensor container 470 and the sensor container tube are located 180 ° rotationally about the centre-line axis of the MFD 1 from the Deuterium and Tritium fuel storage and pellet manufacturing container 379 and the Deuterium and Tritium fuel storage and pellet manufacturing inj ection tube 55 , respectively, as shown in Figures 6a and 6b and 6c .

[0304] Unfortunately, the 14 . 1MeV fusion neutrons produced by the fusion reactions within the MFD reactor 467 can also travel up the sensor container tube and into sensor container 470 , and are captured and thermali zed in the LMLi-Pb Tritium breeding blanket where the neutron kinetic energy is trans formed into heat energy and collected by the Helium coolant flowing in the double walls of the double-walled 17Li- 83Pb Tritium breeding box that is releasably and securely attached to the end of the sensor container 470 , not shown in Figure 1 and Figures 6a and 6b and 6c . Ignition stage 24 . 1 - Primary divertor systems operational .

[0305] Collectively, the concentrically arranged and interconnected primary divertor Helium cooled Tungsten backplates 7 , and the primary divertor Helium cooled Tungsten energy dump targets 8 , and the primary divertor Helium cooled Tungsten power exhaust and momentum loss region targets 9 , and the primary divertor Helium cooled Tungsten baf fles 10 , and the primary divertor Helium cooled Tungsten central dome 11 , and the primary divertor Helium cooled Tungsten backplate central dome 13 , and the primary divertor Helium cooled Tungsten central dome power exhaust and momentum loss region targets 15 , and the primary divertor Helium cooled transparent liner pumping plate 16 , and the primary divertor Helium cooled Tungsten central dome power exhaust and momentum loss region target backplates 19 , and the primary divertor Helium cooled pumping channels 18 , 29 , and the primary divertor vacuum chamber pumping channels 33 , create a circular cross-section gas target primary divertor that is releasably and securely attached to the MFD reactor inner vacuum chamber 2 of the MFD reactor 467 of the MFD, as shown in Figures 4a and 4b and 4c .

[0306] Complex atomic physics processes occur within the gas target primary divertor, including the ioni zation zone 506 , 507 , where the concentric plasma separatrix 504 , 505 temperature starts to decrease due to the radiation losses , and where the impurity seeding neutral gas , such as Argon, Neon, Krypton, Xenon density increases rapidly, and the plasma in the ioni zation zone 506 , 507 is then directed by the magnetic field generated by the primary divertor end external moveable actively cooled sweeping electromagnetic field coil 108 and the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 114 into the recombination zone 508 , 509 . In the recombination zone 508 , 509 , the plasma separatrix 504 , 505 temperature and density rapidly decrease due to the momentum losses through collisions and charge exchange atomic physics processes with impurity seeding neutral gas molecules by the concentric plasma separatrix 504 , 505 .

[0307] The remaining high energy ions and electrons within the concentric plasma separatrix 504 , 505 that collide with the primary divertor Helium cooled Tungsten energy dump targets 8 , lay within the primary divertor Helium cooled Tungsten energy dump target areas 510 , 511 .

[0308] The magnetic field lines generated by the field coil 108 and the field coil 114 can be used to magnetically sweep the primary divertor Helium cooled Tungsten energy dump target strike areas 510 , 511 to reduce the heat energy loading on the primary divertor Helium cooled Tungsten energy dump targets 8 .

[0309] The concentric high recycling region 512 , 513 is a region where there is neutrali zation of the plasma on the primary divertor Helium cooled Tungsten energy dump targets 8 , and volumetric plasma recombination, and ioni zation of the resulting neutrals and where the necessary plasma power is available to sustain the ioni zation process .

[0310] Argon, Helium and other impurities are then pumped out through the primary divertor Helium cooled pumping channels 18 , 29 , and through the primary divertor Helium cooled transparent liner pumping plate 16 and out through the primary divertor vacuum chamber pumping pipework 23 that is connected to the MFP inlet 291 , as shown in Figure 3 , Figures 4a and 4b and 4c and Figures 5a and 5b . Stage 24 .2 - Secondary divertor systems operational .

[0311] Collectively, the concentrically arranged and interconnected secondary divertor Helium cooled Tungsten backplates 34 , and the secondary divertor Helium cooled Tungsten energy dump targets 36 , and the secondary divertor Helium cooled Tungsten power exhaust and momentum loss region targets 37 , and the secondary divertor Helium cooled Tungsten baf fles 38 , and the secondary divertor Helium cooled Tungsten central dome 12 , and the secondary divertor Helium cooled Tungsten backplate central dome 14 , and the secondary divertor Helium cooled Tungsten central dome power exhaust and momentum loss region targets 40 , and the secondary divertor Helium cooled transparent liner pumping plate 17 , and the secondary divertor Helium cooled Tungsten central dome power exhaust and momentum loss region target backplates 35 , and the secondary divertor Helium cooled pumping channels 41 , 42 , create a circular cross-section gas target secondary divertor that is releasably and securely attached to the MFD reactor inner vacuum chamber 2 of the MFD reactor 467 of the MFD, as shown in Figures 4a and 4b and 4c .

[0312] Complex atomic physics processes occur within the gas target secondary divertor, including the ioni zation zone 518 , 519 , where the concentric plasma separatrix 516 , 517 temperature starts to decrease due to the radiation losses , and where the impurity seeding neutral gas , such as Argon, Neon, Krypton, Xenon density increases rapidly, and the plasma in the ioni zation zone 518 , 519 is then directed by the magnetic field generated by the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil 112 and the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 into the recombination zone 520 , 521 . In the recombination zone 520 , 521 , the plasma separatrix 516 , 517 temperature and density rapidly decrease due to the momentum losses through collisions and charge exchange atomic physics processes with impurity seeding neutral gas molecules by the concentric plasma separatrix 516 , 517 .

[0313] The remaining high energy ions and electrons within the concentric plasma separatrix 516, 517 that collide with the secondary divertor Helium cooled Tungsten energy dump targets 36 , lay within the secondary divertor Helium cooled Tungsten energy dump target areas 522 , 523 .

[0314] The magnetic field lines generated by the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil 112 and the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 can be used to magnetically sweep the secondary divertor Helium cooled Tungsten energy dump target areas 522 , 523 to reduce the heat energy loading on the secondary divertor Helium cooled Tungsten energy dump targets 36 .

[0315] The concentric high recycling region 524 , 525 is a region where there is neutrali zation of the plasma on the secondary divertor Helium cooled Tungsten energy dump targets 36 , and volumetric plasma recombination, and ioni zation of the resulting neutrals and where the necessary plasma power is available to sustain the ioni zation process .

[0316] Argon, Helium and other impurities are pumped out through the secondary divertor pumping channels 41 , 42 , and through the secondary divertor Helium cooled transparent liner pumping plate 17 and out through the secondary divertor vacuum chamber pumping pipework 24 that is connected to the MFP inlet 447 , as shown in Figure 3 , Figures 4a and 4b and 4c and Figures 6a and 6b and 6c . Ignition stage 25 D+T Lawson criterion achieved, and D+T fusion reactivity .

[0317] Collectively, the central plasma region 192 will be compressed and will heat up and will be reduced in volume until the Lawson criteria (= plasma density x plasma temperature x energy confinement time ) within the central plasma region 192 are high enough for fusion reactions to occur, which will result in the creation of the magnetically compressed central fusion plasma volume 471 , as shown in Figures 7a and 7b, which will release 14 . 1 MeV neutrons and 3 . 5 MeV alpha particles (Helium-4 ) .

[0318] Collectively, the left central plasma region 193 will be compressed and will heat up and will be reduced in volume until the Lawson criteria within the left central plasma region 193 are high enough for fusion reactions to occur, which will result in the creation of the magnetically compressed primary divertor end fusion plasma volume 472 , as shown in Figures 7a and 7b, which will release 14 . 1 MeV neutrons and 3 . 5 MeV alpha particles (Helium-4 ) .

[0319] Collectively, the right central plasma region 194 will be compressed and will heat up and will be reduced in volume until the Lawson criteria within the right central plasma region 194 are high enough for fusion reactions to occur, which will result in the creation of the magnetically compressed secondary divertor end fusion plasma volume 473 , as shown in Figures 7a and 7b, which will release 14 . 1 MeV neutrons and 3 . 5 MeV alpha particles (Helium-4 ) .

[0320] Ignition stage 26 - Neutrons released / absorbed in 17Li -83Pb breeder blanket .

[0321] The four LMLi-Pb Tritium breeding blanket layers 57 , 59 , 61 ,

[0322] 63 have to be thick enough, an estimated 800mm thick, to capture and thermalize as many of the 14.1MeV fusion neutrons produced by the fusion reaction within the MFD reactor 467. The four layers 57, 59, 61, 63 also shield the MFD reactor outer casing 64 from excessive neutrons and gamma rays radiation damage and reduces occupational exposure to acceptable limits. The four layers 57, 59, 61, 63 also should have the highest possible Tritium breeding ratio TBR and the highest possible blanket energy gain. As the neutrons are slowed in the four layers 57, 59, 61, 63, the neutron kinetic energy is transformed into heat energy and collected by the Helium coolant flowing in the three concentric layers of Helium cooling tubes 58, 60, 62 that act as a Helium heat exchanger .

[0323] The sloped outer shape of the MFD reactor outer casing 64 is analogous to sloped armour in operation and is deliberately designed to maximise the line-of-sight thickness of the four blanket layers 57, 59, 61, 63 relative to the central longitudinal axis of the MFD reactor 467 where the majority of the 14.1MeV neutrons will be produced, so enhancing the capture and thermalization of as many of the 14.1MeV neutrons produced by the fusion reactions within the MFD reactor 467 as possible .

[0324] Heat proof neutron shielding epoxy-based resins that contain boron such as Krafton-HB4® and Eponite®, and neutron reflectors and neutron moderators such as Magnesium Oxide or Beryllium could also be applied to the outer surface of the MFD reactor outer casing 64.

[0325] Stage 27 - Heat transfer from breeder blanket to Helium coolant .

[0326] As the 14.1MeV neutrons are slowed in the four blanket layers 57, 59, 61, 63, the neutron kinetic energy is transformed into heat energy and collected by the Helium coolant flowing in the three concentric layers of Helium cooling tubes 58, 60, 62.

[0327] Mounted equidistantly between the MFD reactor outer casing 64, and the MFD reactor inner vacuum chamber 2 are three concentric layers of Helium cooling tubes 58, 60, 62 that are designed to act as a Helium heat exchanger within the four blanket layers 57, 59, 61, 63, as shown in Figure 3 and Figures 4a and 4b and 4c.

[0328] The three concentric layers are suspended in place to the MFD reactor outer casing 64, using connector arms, which are not shown in Figures 4a and 4b and 4c or Figures 7a and 7b. Figures 4a and 4b and 4c and Figures 7a and 7b shows that three concentric layers of tubes 58, 60, 62 are used in the MFD reactor 467 of the MFD 1, although more or less than three layers could be used to maximise and optimise the amount of heat transfer between the LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63 and the cooling tubes 58, 60, 62.

[0329] The breeder blanket cool Helium coolant upper pump 68 pumps cooled Helium coolant into the Helium transfer upper inlet pipework 65, 66, 67 and the cooled Helium coolant absorbs heat energy from the four LMLi-Pb Tritium breeding blanket layers 57, 59, 61, 63 as the coolant travels through the three concentric layers of tubes 58, 60, 62, respectively, bidirectionally and downwards, as shown in Figures 4a and 4b and 4c. The heated Helium coolant in the three concentric layers of Helium cooling tubes 58, 60, 62 eventually reaches the

[0330] Helium transfer lower outlet pipework 70, 71, 72 and the

[0331] Helium transfer lower outlet pipework 73, 74, 75, which is transferred by pipework to the breeder blanket heated Helium coolant upper pump 69 and the breeder blanket heated Helium coolant lower pump 76, respectively. The breeder blanket cool Helium coolant lower pump 77 pumps cooled Helium coolant into the Helium trans fer upper inlet pipework 78 , 79 , 80 and the coolant absorbs heat energy from the four LMLi-Pb Tritium breeding blanket layers 57 , 59 , 61 , 63 as the coolant travels through the layers of tubes 58 , 60 , 62 , respectively, bi-directionally and downwards , as shown in Figures 4a and 4b and 4c . The heated Helium coolant in the three concentric layers of Helium cooling tubes 58 , 60 , 62 eventually reaches the Helium trans fer lower outlet pipework 70 , 71 , 72 and the Helium trans fer lower outlet pipework 73 , 74 , 75 , which is trans ferred by pipework to the breeder blanket heated Helium coolant upper pump 69 and the breeder blanket heated Helium coolant lower pump 76 , respectively, as shown in Figures 4a and 4b and 4c .

[0332] Helium is a very good choice for coolant within the MFD 1 due to the chemical inertness of Helium . Helium also has a low neutron cross-section and is compatible with other materials used for sub-systems within the MFD 1 . Helium also has a high temperature capability and has a relatively high heat trans fer coef ficient that enables high thermodynamic ef ficiencies . The MFD 1 will also be able to manufacture its own Helium from the Deuterium and Tritium fusion reactions and Helium is stored in the Helium storage systems 237 , 246 . As Helium is a non- metallic coolant it will not be af fected by the magnetic field created within the MFD 1 .

[0333] Ignition stage 28 . 1 - Helium heat exchanger 1 operational .

[0334] Heated Helium, that has had Tritium and other impurities removed by the Helium Tritium separator 236 , is then trans ferred by pipework through the Helium heat exchanger outer wall 211 and through the Helium heat exchanger air gap 212 and through the Helium heat exchanger inner wall 213 into the Helium heat exchanger hot-to-cold pipework 215 . As the heated Helium travels along and through the pipework 215 , heat energy from the heated Helium is trans ferred to the cooled Helium that travels in the opposite direction along and through the Helium heat exchanger cold-to-hot pipework 214 , as shown in Figures 5a and 5b . Cooled Helium is pumped into the Helium heat exchanger cold-to-hot pipework 214 by the cooled Helium pump 209 . Heated Helium is pumped out of the Helium heat exchanger cold-to-hot pipework 214 by the heated Helium pump 226 . Cooled Helium is pumped out of the Helium heat exchanger hot-to-cold pipework 215 by the breeder blanket cool Helium coolant lower pump 77 .

[0335] Ignition stage 28 .2 - Helium heat exchanger 2 operational .

[0336] Heated Helium that has had Tritium and other impurities removed by the Helium Tritium separator 335 is then trans ferred by pipework through the Helium heat exchanger outer wall 347 and through the Helium heat exchanger air gap 348 and through the Helium heat exchanger inner wall 349 and into the Helium heat exchanger hot-to-cold pipework 351 . As the heated Helium travels along and through the pipework 351 , heat energy from the heated Helium is trans ferred to the cooled Helium that travels in the opposite direction along and through the Helium heat exchanger cold-to-hot pipework 350 , as shown in Figures 6a and 6b and 6c . Cooled Helium is pumped into the Helium heat exchanger cold-to-hot pipework 350 by the cooled Helium pump 346 . Heated Helium is pumped out of the Helium heat exchanger cold-to-hot pipework 350 by the heated Helium pump 327 . Cooled Helium is pumped out of the Helium heat exchanger hot-to-cold pipework 351 by the breeder blanket cool Helium coolant upper pump 68 , as shown in Figures 4a and 4b and 4c and Figures 6a and 6b and 6c . The Helium heat exchangers could be used as a 17Li-83Pb desolidification system to ensure that the 17Li-83Pb is always kept above its 235°C melting point.

[0337] Ignition stages 29.1, 29.2 - Two heated Helium A.P.U operational and Two A.P.U's backups operational.

[0338] The MFD 1 sub-systems can all be powered by its four auxiliary power units 195, 249, 355, 375, and if the MFD 1 requires external electrical power to power its sub-systems in order to achieve fusion ignition, the auxiliary power units 195, 249, 355, 375 are interconnected with an external power source cable 561 that is attached to an external power source socket 551. The external power source socket 551 could be interconnected to external electrical power supplies, not shown in Figure 3.

[0339] The auxiliary power units 195, 249, 355, 375 could utilize Helium heat exchanger high by-pass turbofan engines, not shown in Figure 3, that are designed to be powered by the Helium coolant that is heated by the two Helium heat exchangers within the MFD 1, as shown in Figure 3. Current small turboshaft engines, that have a combustion chamber that combusts fossil fuel, are currently used within auxiliary power units such as the Pratt & Whitney Canada's PW980 auxiliary power unit (APU) , not shown in Figure 3. The combustion chamber found in existing high by-pass turbofan engines is replaced in the MFD 1 Helium heat exchanger high by-pass turbofan engine by Helium heat exchanger pipework that consists of multiple rows of concentrically arranged pipework that are located in the Helium heat exchanger chamber, not shown in Figure 3. Alternatively, the auxiliary power units 195, 249, 355, 375 could utilize heated Helium closed Brayton cycle (CBC) gas turbine auxiliary power units, as shown in Figure 11, whose rotating sub-systems consist of an intercooled Helium turbocompressor coupled to an electrical generator, which are all housed in an auxiliary unit housing that contains recuperators, intercoolers, precoolers, and which have been highly developed for use with high temperature Helium cooled fission reactors by General Atomics®. It is estimated that the four auxiliary power units 195, 249, 355, 375 could utilise heated Helium to produce the many MegaWatts of electrical power that are required for the steady state operation of the sub-systems of the MFD 1.

[0340] Alternatively, the auxiliary power units 195, 249, 355, 375 could utilize one or more Rolls-Royce® / MTU® gas turbine powered electrical generators or one or more Rolls-Royce® / MTU® gas-to-liquid / hydrocreated vegetable oil / diesel engine powered electrical generators. The auxiliary power units 195, 249,

[0341] 355, 375 have double-walled with pressurised air gap air intakes 196, 250, 356, 376, respectively, and double-walled with pressurised air gap exhausts 197, 251, 357, 377, respectively, that releasably and securely pass through the MFD inner casing 549 and the MFD central casing 545 and the MFD outer casing 541. These fossil-fuelled electrical generators could be used as start-up or emergency back-up electrical generators by the MFD 1, so eliminating the need for an external electrical power source such as a ground power unit GPU, as described in stage 1, for example.

[0342] Ignition stage 30 plasma heating methods reduced as Q=1 ,

[0343] Q>5, Q>20.

[0344] After fusion ignition has been achieved within the MFD reactor

[0345] 467, the electrical power to the seven plasma heating systems can be reduced or deactivated and any external power source (not shown in Figure 3 ) can be disconnected from the external power source socket 551 . The external power source socket 551 , as shown in Figure 3 , is attached to the external power source cable 561 that is interconnected with the auxiliary power units 195 , 249 , 355 , 375 . The four auxiliary power units 195 , 249 , 355 , 375 should then be suf ficient to generate the electrical power required for the steady-state sel f-heating fusion ignition operation of the MFD 1 .

[0346] The MFD 1 is designed to achieve a high plasma power ampli fication factor Q which is the ratio of the electrical power produced by the MFD 1 from fusion reactions and the electrical power required to power the MFD 1 sub-systems . Q=1 is known as breakeven and the plasma will cool without external heating . Q>5 is known as engineering breakeven and is sel f-heating fusion ignition . Q>20 is known as economic breakeven, and is where the integrated MFD 1 design should be able to sell surplus electricity that it produces .

[0347] Pod and rear domed section and opening systems .

[0348] The MFD 1 has a MFD inner casing 549 that is separated by the MFD inner air gap 547 from the MFD central casing 545 . The MFD central casing 545 is separated by the MFD outer air gap 543 from the MFD outer casing 541 . Hollow spacers 535 , 536 , 537 , 538 located within the MFD inner air gap 547 and within the MFD outer air gap 543 , ensure that the MFD inner casing 549 and the MFD central casing 545 and the MFD outer casing 541 are equidistantly separated from one another, as shown in Figure 3 .

[0349] The MFD inner casing rear domed section 550 and the MFD central casing rear domed section 546 and the MFD outer casing rear domed section 542 can all be collectively opened using the powered vacuum tight hinges 552 for accessibility and maintenance purposes . The MFD 1 has a MFD inner casing rear domed section 550 that is separated by the MFD rear domed section inner air gap 548 from the MFD central casing rear domed section 546 . The MFD central casing rear domed section 546 is separated by the MFD rear domed section outer air gap 544 from the MFD outer casing rear domed section 542 . Hollow spacers 539 , 540 located within the MFD rear domed section inner air gap 548 and within the MFD rear domed section outer air gap 544 ensure that the MFD inner casing rear domed section 550 and the MFD central casing rear domed section 546 and the MFD outer casing rear domed section 542 are equidistantly separated from one another, as shown in Figure 3 .

[0350] The MFD attachment 555 is releasably and securely attached to the upper outside surface of the MFD outer casing 541 . The MFD attachment 555 is shown in Figure 3 to have a MFD flat upper attachment surface 558 , so allowing the MFD ID shown in Figure 10 to be mounted either externally or semi-recessed or internally within the blended wing body BWB aircraft 580 , for example . Alternatively, the MFD attachment 555 could be fitted to an underwing attachment or a fuselage attachment of a conventional aircraft such as an Airbus® A380 , not shown in Figure 10 .

[0351] Sliding sub-systems from pod

[0352] Collectively, the interconnected MFD support sub-systems 468 of the MFD 1 , and the MFDRP outer wall 228 and the MFDRP inner wall 230 , and the MFD reactor 467 of the MFD 1 , and the MFDRP outer wall 326 and the MFDRP inner wall 324 , and the MFD support and fuel inj ection sub-systems 469 of the MFD 1 are all designed to be slid into and out of the MFD 1 inner casing 549 as one complete slideable module when required for reliability, accessibility, maintainability, inspectability (R .A.M . I ) , sub-system upgrades and maintenance purposes ( see sliding raft SR of Figure 1 ) , by opening the multi-layered pressurised rear access hatch MLH . The MFDRP outer wall 228 and the MFDRP inner wall 230 and the MFDRP outer wall 326 and the MFDRP inner wall 324 can all be releasably and securely attached to the MFD inner casing 549 using fasteners not shown in Figure 3 .

[0353] Aerodynamic and ballistic protection and environmental protection features .

[0354] The MFD outer casing 541 and the MFD outer casing rear domed section 542 and the MFD attachment 555 are designed to have the lowest possible aerodynamic drag coef ficient so that the MFD 1 can be fitted to the underside of large manned or unmanned aircraft fuselages or wings when required with the minimal increase in drag to the large manned or unmanned aircraft , according to an embodiment .

[0355] The MFD inner casing 549 and the interconnected MFD inner casing rear domed section 550 , and the MFD central casing 545 and the interconnected MFD central casing rear domed section 546 , and the MFD outer casing 541 and the interconnected MFD outer casing rear domed section 542 are collectively designed to maximi ze protection and maximi ze ballistic protection to the MFD support sub-systems 468 and the MFD reactor 467 and the MFD support and fuel inj ection sub-systems 469 of the MFD 1 from external obj ects and threats .

[0356] The MFD inner casing 549 and the interconnected MFD inner casing rear domed section 550 , and the MFD central casing 545 and the interconnected MFD central casing rear domed section 546 , and the MFD outer casing 541 and the interconnected MFD outer casing rear domed section 542 are also collectively designed to minimise the environmental acoustic noise pollution and acoustic noise signature of manned or unmanned sub-sea, sea, land, aerial-based platforms fitted with a MFD 1 .

[0357] Examples :

[0358] For the mobile fusion device 1 land-based variant , as shown in Figure 8 , it is estimated that the MFD reactor 467 has a length A of 8m, and has an outer diameter D of 5m . The MFD reactor 467 and the MFD support sub-systems 468 and the MFD support and fuel inj ection sub-systems 469 have a combined length B of 30m . The mobile fusion device 1 has a total length

[0359] C of 40m, and has an outer diameter E of 6m, and has an estimated mass of 700 tonnes for a land-based and sea-based platforms variant and approximately 200 tonnes for an aerial platform variant . This means that the MFD 1 is transportable by road on sel f-propelled multi-axle modular transporter vehicles so enabling MFDs 1 to be transported by road from their construction factory to either shipping ports or to where they need to be located either near the coastline or inland globally .

[0360] The MFD reactor inner vacuum chamber 2 is called the structural plasma facing material and the MFD reactor outer casing 64 could be manufactured from a Vanadium Chromium

[0361] Titanium alloy that are highly resistant to swelling from radiation and Helium production and has low Helium embrittlement at temperatures of up to 750 ° C .

[0362] The fusion of Deuterium and Tritium produces 3 . 5MeV alpha particles (Helium-4 ) and 14 . 1MeV neutrons which are captured and thermalised by the Lithium in the liquid metal 17Li- 83Pb breeder blanket to produce more Tritium and Helium-4 . Liquid metal 17Li- 83Pb is recommended as a breeder blanket as it has very good Tritium breeding capabilities and the Lead within the LMLi-Pb enhances the Tritium breeding ratio by acting as a neutron multiplier . Tritium is also radioactive and has a hal f-li fe of 12 . 6 years and emits Beta radiation which involves one of its neutrons trans forming into a proton and releasing an electron, so trans forming the Tritium very slowly into Helium-3 .

[0363] Pressurised Helium (Helium-4 ) is a very good choice for coolant within the MFD 1 due to its chemical inertness and its low neutron cross-section . It is compatible with other materials , has a high temperature capability, has a relatively high heat trans fer coef ficient and is a non-metallic coolant so it will not be af fected by the magnetic field created within the MFD 1 .

[0364] The large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket-encapsulated superconducting electromagnetic field coils 123 , 147 , and the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 may be manufactured from Niobium-Tin (Nb3Sn) or Niobium-Titanium (Nb-Ti ) and will become superconducting when cooled with supercritical Helium in the range of 4 . 5 Kelvin ( -268 . 5 ° C ) .

[0365] In the future it may be poss ible to use superconducting materials that will become superconducting when cooled to much higher temperatures above 4 . 5K, so reducing the need and power for associated Helium cryogenic cooling systems .

[0366] It is estimated that the primary divertor end external moveable actively cooled sweeping electromagnetic field coil 108 and the primary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 114 each have an estimated current rating of 8 MegaAmpTurns and they collectively create the magnetic mirror point 499 .

[0367] It is estimated that the secondary divertor end external moveable actively cooled magnetic mirror electromagnetic field coil 160 , and the secondary divertor end external moveable actively cooled sweeping electromagnetic field coil 112 each have an estimated current rating of 8 MegaAmpTurns and they collectively create the magnetic mirror point 500 .

[0368] It is estimated that the small external moveable actively cooled electromagnetic field coils 116 , 118 , 120 , 128 , 146 , 154 , 156 , 158 each have an estimated current rating of 0 . 5 MegaAmpTurns .

[0369] It is estimated that the large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic field coils 123 , 147 , and the very large external moveable pressurised Helium cooled superconducting electromagnetic field coil 135 each have an estimated current rating of 8 MegaAmpTurns .

[0370] External transferred of cooled / heated Helium to , from the MFD .

[0371] The MFD 1 is designed to accept and heat cooled Helium from Helium and steam heat exchanger 567A, as shown in Figure 8 , and is designed to accept and heat cooled Helium from Helium and steam heat exchangers 567B, 567C, as shown in Figure 9 , and is designed to accept and heat cooled Helium from Helium and heated air heat exchanger high by-pass turbofan engines

[0372] 581A, 581B, as shown in Figure 10 , and is designed to accept and heat cooled Helium from a heated Helium closed Brayton cycle ( CBC ) electrical power system 589 , as shown in Figure 11 .

[0373] The cooled Helium pipework 556 trans fers cooled Helium to the cooled Helium pump 209 that pumps the cooled Helium into the Helium heat exchanger cold-to-hot pipework 214 , as shown in Figures 5a and 5b .

[0374] Heated Helium is pumped out of the Helium heat exchanger cold -to-hot pipework 214 by the heated Helium pump 226 . The heated Helium pump 226 trans fers the heated Helium to the heated Helium pipework 557 , as shown in Figure 3 .

[0375] The Helium heat exchanger cold-to-hot pipework 214 is located within the MFD support sub-systems 468 of the MFD 1 that is located within the MFD support sub-systems compartment 553 .

[0376] The cooled Helium pipework 556 and the heated Helium pipework 557 are shown in Figure 3 to pass internally within the front hal f of the MFD flat upper attachment surface 558 of the MFD attachment 555 .

[0377] The cooled Helium pipework 560 trans fers cooled Helium to the cooled Helium pump 346 that pumps the cooled Helium into the Helium heat exchanger cold-to-hot pipework 350 , as shown in Figures 6a and 6b and 6c .

[0378] Heated Helium is pumped out of the Helium heat exchanger cold- to-hot pipework 350 by the heated Helium pump 327 . The heated Helium pump 327 trans fers the heated Helium to the heated Helium pipework 559 .

[0379] The Helium heat exchanger cold-to-hot pipework 350 is located within the MFD support and fuel inj ection sub-systems 469 of the MFD 1 that is located within the MFD support and fuel inj ection sub-systems compartment 554 .

[0380] The heated Helium pipework 559 and the cooled Helium pipework 560 are shown in Figure 3 to pass internally within the rear hal f of the MFD flat upper attachment surface 558 of the MFD attachment 555 .

[0381] Land-based MFD power station .

[0382] Currently, the world ' s many thousands of coal , oil and gas fuelled electricity generating power stations emit approximately 15 Gigatonnes of carbon dioxide annually which is a maj or contributor to global warming . Land-based nuclear fission power stations do not produce greenhouse gases , but past catastrophic fission chain reaction accidents such as 3 Mile I sland, Chernobly, Fukukshima and their production of very long term and very radioactive waste has made them unpopular which has limited their deployment to less than 500 land-based nuclear fission power stations globally .

[0383] It would be environmentally beneficial i f electricity generating power stations could dispense with either combusting fossil fuels or using radioactive fi ssion fuels , and instead were powered by a scaleable , non-polluting, recyclable , non-chain reaction operating land-based MFD electricity generating power station 562 that incorporates a MFD 1A, as shown in Figure 8 .

[0384] The cooled Helium pipework 556A and the heated Helium pipework 557A are shown in Figure 8 to pass through the MFD flat upper attachment surface 558A and to pass internally within the front hal f of the MFD attachment 555A.

[0385] The heated Helium pipework 559A and the cooled Helium pipework 560A are shown in Figure 8 to pass through the MFD flat upper attachment surface 558A and to pass internally within the rear hal f of the MFD attachment 555A.

[0386] The heated Helium pipework 557A and the heated Helium pipework 559A are both releasably and securely interconnected to one another to form the heated Helium coolant pipework 563A. The heated Helium that flows within the heated Helium coolant pipework 563A is then trans ferred into the interconnected Helium heat exchanger pipework 565A within the Helium and steam heat exchanger 567A. Heat energy from the heated Helium flowing within the Helium heat exchanger pipework 565A is trans ferred to the cool pressuri sed water flowing in the heat exchanger pipework 566A which causes the water to turn to steam within the heat exchanger pipework 566A. The cooled Helium flowing from the Helium heat exchanger pipework 565A is then trans ferred into the cooled Helium coolant pipework 564A that is releasably and securely interconnected to the cooled Helium pipework 556A and to the cooled Helium pipework 560A, as shown in Figure 8 .

[0387] The steam within the heat exchanger pipework 566A is then trans ferred by pipework from the Helium and steam heat exchanger 567A and into the steam turbine 568A that rotates an interconnected steam turbine shaft 569A that rotates an interconnected electrical generator 570 . The electricity produced by the electrical generator 570 is then trans ferred by high power electrical transmission lines 572 from the power station containment building 571 to the high voltage overhead pylons 573 , as shown in Figure 8 .

[0388] The MFD 1A and the Helium and steam heat exchanger 567A and the steam turbine 531A568A and the electrical generator 570 are all releasably and securely attached to the power station containment building 571 using shock-absorbing seismic isolator pads , not shown in Figure 8 , and the power station containment building 571 is located on ground 574 .

[0389] The land-based MFD electricity generating power station 562 that incorporates a MFD 1A that is shown in Figure 8 , does not use any highly radioactive fissile fuel and does not release radioactive materials to the environment like existing fission-based nuclear power stations . The land-based MFD electricity generating power station 562 would also be immune from a catastrophic fission reactor type nuclear meltdown accident and would not emit vast amounts of polluting greenhouse gases that conventional fossil fuel combustion power stations produce . Ship MFD propulsion system.

[0390] Currently, there are approximately 60 , 000 large commercial ships and warships globally that all combust either high sulphur content and black carbon particulates producing heavy bunker fuel oil or diesel fuel or boil of f gas fossil fuels in their propulsion units . The environmental impact of shipping includes air pollution, ballast water pollution, very long distance acoustic pollution and oil pollution . Green shipping fuels produced from renewable electricity such as hydrogen and e-ammonia are existing alternatives that could assist to decarbonise this marine propulsion sector, but they are expensive to produce compared to the relatively cheap, heavy, dirty, high-carbon fuel oil .

[0391] It would be environmentally beneficial i f large commercial ships and warships in the near future could dispense with combusting fossil fuels and instead were powered by a scaleable , non-polluting, recyclable , and low acoustic signature mobile fusion device IB .

[0392] Figure 9 shows a cutaway side view of a large container carrying ship 575 floating on the sea surface 577 that is fitted with a MFD IB .

[0393] The cooled Helium pipework 556B and the heated Helium pipework 557B are shown in Figure 9 to pass through the MFD flat upper attachment surface 558B and pass internally within the front hal f of the MFD attachment 555B .

[0394] The heated Helium pipework 559B and the cooled Helium pipework 560B are shown in Figure 9 to pass through the MFD flat upper attachment surface 558B and pass internally within the rear hal f of the MFD attachment 555B .

[0395] The heated Helium pipework 557B and the heated Helium pipework 559B are both releasably and securely interconnected to one another to form the heated Helium coolant pipework 563B . The heated Helium that flows within the heated Helium coolant pipework 563B is then trans ferred into the interconnected Helium heat exchanger pipework 565B within the Helium and steam heat exchanger 567B . Heat energy from the heated Helium flowing in the Helium heat exchanger pipework 565B is trans ferred to the cool pressuri sed water flowing in the heat exchanger pipework 566B which causes the water to turn to steam within the heat exchanger pipework 566B . The cooled Helium flowing from the Helium heat exchanger pipework 565B is then trans ferred into the cooled Helium coolant pipework 564B that is releasably and securely interconnected to the cooled Helium pipework 556B and to the cooled Helium pipework 560B .

[0396] The steam within the heat exchanger pipework 566B is then trans ferred by pipework from the Helium and steam heat exchanger 567B and into the steam turbine 568B that rotates an interconnected steam turbine shaft and gearbox 569B that rotates a propeller 576 which propels the large container carrying ship 575 across the sea surface 577 .

[0397] Submarine MFD propulsion system.

[0398] Currently, nuclear powered submarines are powered by pressurised water fission-based nuclear reactors that use highly radioactive enriched Uranium fuel that generates highly radioactive waste when refuelled or decommissioned, and whose hal f-li fe is many millions of years . Conventionally powered submarines can either have an internal fuel capacity of several hundred tonnes of marine diesel fuel and rechargeable batteries i f powered by a diesel electric propulsion system, or an air independent propulsion system that utilises limited li fe-time fuel cells .

[0399] It would be environmentally and economically beneficial i f submarines in the future could dispense with combusting fossil fuels , fuel cells and pressurised water fission-based nuclear reactors and instead were powered by a scaleable , nonpolluting, recyclable , and low acoustic signature mobile fusion device 1C .

[0400] Figure 9 shows a cutaway side view of a submarine 578 operating beneath the sea surface 577 that is fitted with a MFD 1C .

[0401] The cooled Helium pipework 556C and the heated Helium pipework 557C are shown in Figure 9 to pass through the MFD flat upper attachment surface 558C and pass internally within the front hal f of the MFD attachment 555C .

[0402] The heated Helium pipework 559C and the cooled Helium pipework 560C are shown in Figure 9 to pass through the MFD flat upper attachment surface 558C and pass internally within the rear hal f of the MFD attachment 555C .

[0403] The heated Helium pipework 557C and the heated Helium pipework 559C are both releasably and securely interconnected to one another to form the heated Helium coolant pipework 563C . The heated Helium that flows within the heated Helium coolant pipework 563C is then trans ferred into the interconnected Helium heat exchanger pipework 565C within the Helium and steam heat exchanger 567C . Heat energy from the heated Helium flowing in the Helium heat exchanger pipework 565C is trans ferred to the cool pressuri sed water flowing in the heat exchanger pipework 566C which causes the water to turn to steam within the heat exchanger pipework 566C . The cooled Helium flowing from the Helium heat exchanger pipework 565C is then trans ferred into the cooled Helium coolant pipework 564C that is releasably and securely interconnected to the cooled Helium pipework 556C and to the cooled Helium pipework 560C .

[0404] The steam within the heat exchanger pipework 566C is then trans ferred by pipework from the Helium and steam heat exchanger 567C and into the steam turbine 568C that rotates an interconnected steam turbine shaft and gearbox 569C that rotates a pump j et propulsor 579 which propels the submarine 578 with as low an hydroacoustic signature as possible under the sea surface 577.

[0405] The large container carrying ship 575 and the submarine 578 shown in Figure 9 are not to scale .

[0406] Aircraft-based platform MFD propulsion system.

[0407] Currently, approximately 26 , 000 airliners are operational globally, and airliners such as the Airbus ® A380 can have an internal fuel capacity of over 250 tonnes of aviation fuel for their high by-pass turbofan engines propulsion systems , not shown in Figure 10 . A converted Convair ® NB-36H bomber aircraft had 47 test flights transporting an operating fission nuclear powerplant , but the proj ect was cancelled for a variety of reasons including its potentially catastrophic risk of a fission chain reaction explosion and contamination .

[0408] It would therefore be environmentally and economically beneficial i f airliners and large military aircraft in the future could dispense with combusting fossil fuels that have been shown to be a large contributor to global warming, and instead were powered by a scaleable , non-polluting, recyclable mobile fusion device ID that has no catastrophic explosion risk associated with fission nuclear powerplants .

[0409] Figure 10 shows a top view of a blended wing body BWB aircraft 580 that is fitted with a centrally and internally mounted MFD ID and two rear fuselage mounted Helium and heated air heat exchanger high by-pass turbofan engines 581A, 581B .

[0410] The cooled Helium pipework 556D and the heated Helium pipework 557D are shown in Figure 10 to pass through the MFD flat upper attachment surface 558D and pass internally within the front hal f of the MFD attachment 555D .

[0411] The heated Helium pipework 559D and the cooled Helium pipework 560D are shown in Figure 10 to pass through the MFD flat upper attachment surface 558D and pass internally within the rear hal f of the MFD attachment 555D .

[0412] The heated Helium pipework 557D and the heated Helium pipework 559D are both releasably and securely interconnected to one another to form the heated Helium coolant pipework 563D . The heated Helium that flows within the heated Helium coolant pipework 563D is then trans ferred to the Helium heat exchangers within the Helium and heated air heat exchanger high by-pass turbofan engines 581A, 581B, as shown in Figure 10 , that replaces the combustion chamber found in existing fossil- fuel powered turbofan engines .

[0413] Heat energy is trans ferred from the Helium heat exchangers within the Helium and heated air heat exchanger high by-pass turbofan engines 581A, 581B to the high pressure air that is directed over the Helium heat exchangers within the Helium and heated air heat exchanger high by-pass turbofan engines 581A, 581B .

[0414] The cooled Helium that has passed through the Helium heat exchangers within the Helium and heated air heat exchanger high by-pass turbofan engines 581A, 581B is then trans ferred into the cooled Helium coolant pipework 564D that is releasably and securely interconnected to the cooled Helium pipework 556D and to the cooled Helium pipework 560D, as shown in Figure 10 .

[0415] The heated air that exits the Helium heat exchangers within the Helium and heated air heat exchanger high by-pass turbofan engines 581A, 581B is used to rotate faster the Helium and heated air heat exchanger high by-pass turbofan enginse 581A, 581B interconnected internal turbine blades and compressor blades which increases the Helium and heated air heat exchanger high by-pass turbofan engines 581A, 581B continuous process of air intake , compression, heating, expansion, expulsion and thrust for the blended wing body BWB aircraft 580 shown in Figure 10 .

[0416] Space-based platform MFD propulsion system.

[0417] Currently, space-based platforms such as satellites and spacestations use a diverse array of propulsion systems that provides a speci fic impulse ( the propellant velocity divided by the standard gravitational acceleration 9 . 81m / second2) and a maximum Av ( the maximum change of velocity of the spacecraft ) , including : magnetohydrodynamic propulsion systems , nuclear fission propulsion systems , electromagnetic electric propulsion systems , electrothermal electric propulsion systems , electrostatic electric propulsion systems .

[0418] It would be environmentally and economically beneficial i f spacecraft in the future could dispense with limited propellant-based propulsion systems described previously, that have a limited speci fic impulse and limited maximum Av, and instead were powered by a scaleable , non-polluting, recyclable mobile fusion device IE that could potentially provide a very large speci fic impulse and a much greater Av over much greater mission durations compared to existing spacecraft propulsion systems .

[0419] Figure 11 shows a spacecraft 582 that is fitted with a MFD IE powerplant and directable laser propulsors 591A, 591B that emit laser beams 592A, 592B, respectively, of speed of light photons that are used as a propellant to produce thrust . The spacecraft 582 could be used for very long duration interstellar space missions which will need to have a large and voluminous reinforced crew module 585 that is mounted internally at the front of the reinforced fuselage 584 , that also has reinforced cockpit windows 583 .

[0420] Figure 11 also shows a cutaway view of the MFD IE and the interconnected heated Helium closed Brayton cycle ( CBC ) electrical power system 589 and the interconnected Deuterium storage tank 588 that is used to provide the large volume of Deuterium fuel that the MFD IE will require for long duration space missions . Deuterium can be extracted from seawater by chemical exchange methods and the resulting heavy water Deuterium Oxide is then subj ected to electrolysis using Hydrogen Sulphide which results in the formation of Deuterium gas . Potentially, the MFD IE wi ll produce more Tritium fuel than it consumes by Deuterium Tritium fusion reactions due to its integrated 17Li- 83Pb breeder blanket systems that were described previously .

[0421] The MFD IE will also produce great volumes of Helium which could be stored in a large Helium tank 586 that could be used by manoeuvring Helium space thrusters 587 to steer the spacecraft 582 .

[0422] The cooled Helium pipework 556E and the heated Helium pipework 557E are shown in Figure 11 to pass through the MFD flat upper attachment surface 558E and pass internally within the front hal f of the MFD attachment 555E .

[0423] The heated Helium pipework 559E and the cooled Helium pipework 560E are shown in Figure 11 to pass through the MFD flat upper attachment surface 558E and pass internally within the rear hal f of the MFD attachment 555E .

[0424] The heated Helium pipework 557E and the heated Helium pipework 559E are both releasably and securely interconnected to one another to form the heated Helium coolant pipework 563E . The heated Helium that flows within the heated Helium coolant pipework 563E is trans ferred into the heated Helium closed Brayton cycle ( CBC ) electrical power system 589 , whose rotating sub-systems consist of an intercooled Helium turbocompressor coupled to a permanent magnet electrical generator, which are all housed in an auxiliary unit housing that contains recuperators , intercoolers , precoolers .

[0425] The cooled Helium flowing from the heated Helium closed Brayton cycle ( CBC ) electrical power system 589 is then trans ferred into the cooled Helium coolant pipework 564E that is releasably and securely interconnected to the cooled Helium pipework 556E and to the cooled Helium pipework 560E , as shown in Figure 11 .

[0426] Generally, closed Brayton cycle ( CBC ) electrical power systems are considered as providing the best balance of ef ficiency and mass for planetary and deep space power systems . The heated Helium closed Brayton cycle ( CBC ) electrical power system 589 would provide the operational benefits of very high reliability with a high mean time between failure MTBF, high ef ficiency, scalability to high power ratings , long mission endurance , and could incorporate a permanent magnet electrical generator that could produce electricity that could be trans ferred by power cables 590A, 590B to power a plurality of directable laser propulsors 591A, 591B, respectively, that emit laser beams 592A, 592B, respectively .

[0427] Embodiments of the present invention may provide a mobile fusion device comprising a fusion reactor and support systems , wherein the device has the integrated sub-systems required to achieve fusion ignition, a high power ampli fication factor Q and steady state electricity generation output .

[0428] Embodiments may also provide a mobile fusion device comprising a fusion reactor and support systems whose inherent design flexibility, linear design configuration and sub-systems duplication / redundancy / diversity / modularity, should allow it to be scaled to suit the power needs of customers and diverse platforms that it is fitted to as a fusion powerplant .

[0429] Furthermore , embodiments of the present invention may provide a mobile fusion device comprising a fusion reactor whose variable internal geometry magnetic field lines are inward directed and have a positive outward gradient and are convex shaped and counteract increasing plasma pressure with its radially strengthening magnetic field pressure , so potentially conferring sel f-regulating magnetohydrodynamic stabili zation .

[0430] Whilst endeavouring in the foregoing speci fication to draw attention to those features of the invention believed to be of particular importance , it should be understood that the applicant claims protection in respect of any patentable feature or combination of features referred to herein, and / or shown in the drawings , whether or not particular emphasis has been placed thereon .

Claims

Claims1 . A mobile fusion device , comprising a fusion reactor for fusing atomic nuclei in a plasma of Deuterium and Tritium, a controllable magnetic confinement system for confining the plasma within the reactor, and a plasma heating system for heating the plasma, wherein the plasma heating system is arranged to heat the plasma by a plurality of methods including alpha channelling ef fect heating, in which Helium nuclei created in the plasma by the fusion of Deuterium and Tritium trans fer most of their energy to the plasma before being removed from the plasma .2 . A mobile fusion device according to Claim 1 , wherein the mobile fusion device is arranged to operate in the hot-ion mode .3 . A mobile fusion device , comprising a fusion reactor for fusing atomic nuclei in a plasma of Deuterium and Tritium, a controllable magnetic confinement system for confining the plasma within the reactor, a breeder blanket at least partly surrounding the reactor and arranged to breed Tritium from free neutrons created by the fusion of the Deuterium and the Tritium, and a Helium recycling system arranged to recycle Helium created in the fusion reaction for use in a liquid Helium cooling system .4 . A mobile fusion device compris ing a fusion reactor and support systems , wherein the device comprises a containment pod arranged to house the reactor and the support systems that are slidably mounted in the pod, and wherein the pod has an openable pod hatch .5 . A mobile fusion device according to Claim 4 , wherein the containment pod is multi-layered .6 . A mobile fusion device according to Claim 4 or 5 , wherein the hatch is multi-layered .7 . A mobile fusion device comprising a fusion reactor and support systems mounted in a pod, wherein the pod is mountable on or in a moveable vessel and is aerodynamically shaped .8 . A mobile fusion device according to any of the preceding claims , wherein the device includes two separated and fully integrated and electrically powered Deuterium and Tritium direct internal recycling systems .9 . A mobile fusion device according to any of the preceding claims , wherein the device includes two separated and fully integrated and electrically powered Deuterium and Tritium inner fuel cycle systems ;10 . A mobile fusion device according to any of the preceding claims , wherein the device includes two separated and fully integrated and electrically powered Deuterium and Tritium outer fuel cycle systems ;11 . A mobile fusion device according to any of the preceding claims , wherein the device includes seven fully integrated and electrically powered plasma heating methods .12 . A mobile fusion device according to any of the preceding claims , wherein the device includes external moveable actively cooled electromagnetic field coils and a very large external moveable pressurised Helium cooled superconducting electromagnetic field coil and two large internal stationary pressurised Helium cooled 17Li- 83Pb liquid metal breeder blanket encapsulated superconducting electromagnetic fieldcoils that collectively magnetically confine the plasma within the MFD reactor .13 . A mobile fusion device according to any of the preceding claims , wherein the magnetically confined plasma is magnetically diverted into a fully integrated Helium cooled primary divertor and a fully integrated Hel ium cooled secondary divertor that are located at either end of the MFD reactor .14 . A mobile fusion device according to any of the preceding claims , wherein there is a space between the MFD reactor outer casing and the MFD reactor inner vacuum chamber, and wherein the space has a plurality of LMLi-Pb Tritium breeding blanket layers that have a plurality of concentric layers of pressuri zed Helium cooling tubes .15 . A mobile fusion device according to any of the preceding claims , wherein the device includes two separated fully integrated heated Helium compact heat exchangers .16 . A mobile fusion device according to any of the preceding claims , wherein the device includes four separated fully integrated auxiliary power units .17 . A mobile fusion device according to any of the preceding claims , wherein the device includes sensors arranged to supply information to a control computer that controls the operation of the integrated sub-systems of the MFD .

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