383results about "Reactor heat to mechanical energy" patented technology

The present invention provides a plasma arc torch that can be used for lean combustion. The plasma arc torch includes a cylindrical vessel, an electrode housing connected to the first end of the cylindrical vessel such that a first electrode is (a) aligned with a longitudinal axis of the cylindrical vessel, (b) extends into the cylindrical vessel, and (c) can be moved along the longitudinal axis, a linear actuator connected to the first electrode to adjust a position of the first electrode, a hollow electrode nozzle connected to the second end of the cylindrical vessel such that the center line of the hollow electrode nozzle is aligned with the longitudinal axis of the cylindrical vessel, and wherein the tangential inlet and the tangential outlet create a vortex within the cylindrical vessel, and the first electrode and the hollow electrode nozzle creates a plasma that discharges through the hollow electrode nozzle.

The present invention provides a plasma arc torch that can be used for lean combustion. The plasma arc torch includes a cylindrical vessel, an electrode housing connected to the first end of the cylindrical vessel such that a first electrode is (a) aligned with a longitudinal axis of the cylindrical vessel, (b) extends into the cylindrical vessel, and (c) can be moved along the longitudinal axis, a linear actuator connected to the first electrode to adjust a position of the first electrode, a hollow electrode nozzle connected to the second end of the cylindrical vessel such that the center line of the hollow electrode nozzle is aligned with the longitudinal axis of the cylindrical vessel, and wherein the tangential inlet and the tangential outlet create a vortex within the cylindrical vessel, and the first electrode and the hollow electrode nozzle crate a plasma the discharges through the hollow electrode nozzle.

An In Orbit Transportation & Recovery System (IOSTAR™) (10) One preferred embodiment of the present invention comprises a space tug powered by a nuclear reactor (19). The IOSTAR™ includes a collapsible boom (11) connected at one end to a propellant tank (13) which stores fuel for an electric propulsion system (12). This end of the boom (11) is equipped with docking hardware (14) that is able to grasp and hold a satellite (15) and as a means to refill the tank (13). Radiator panels (16) mounted on the boom (11) dissipate heat from the reactor (19). A radiation shield (20) is situated next to the reactor (19) to protect the satellite payload (15) at the far end of the boom (11). The IOSTAR™ (10) will be capable of accomplishing rendezvous and docking maneuvers which will enable it to move spacecraft between a low Earth parking orbit and positions in higher orbits or to other locations in our Solar System.

An In Orbit Transportation & Recovery System (IOSTAR™) (10). One preferred embodiment of the present invention comprises a space tug powered by a nuclear reactor (19). The IOSTAR™ includes a collapsible boom (11) connected at one end to a propellant tank (13) which stores fuel for an electric propulsion system (12). This end of the boom (11) is equipped with docking hardware (14) that is able to grasp and hold a satellite (15) and as a means to refill the tank (13). Radiator panels (16) mounted on the boom (11) dissipate heat from the reactor (19). A radiation shield (20) is situated next to the reactor (19) to protect the satellite payload (15) at the far end of the boom (11). The IOSTAR™ (10) will be capable of accomplishing rendezvous and docking maneuvers which will enable it to move spacecraft between a low Earth parking orbit and positions in higher orbits or to other locations in our Solar System.

A process to safely convert about 95% of the nuclear waste into a usable fuel source is disclosed. The process, involving a sub-critical power reactor and a proliferation-resistant fuel cycle, consumes depleted uranium or thorium fuel with fissionable fuel, including reactor or weapons-grade plutonium. The reactor is comprised of coaxial neutron and energy-amplifying regions separated by moderating and thermal neutron absorbing layers. Control of the water or gas-cooled reactor is provided by plutonium-helium loops with a variable volume flow rate and an external source of neutrons that quickly reacts to any fluctuations of the reactor parameters. A second embodiment of the invention is a compact sub-critical propulsion reactor utilizing fission electric cell and thermo-acoustic technology for electrical power generation.

A nuclear reactor in which a secondary or tertiary coolant system of a nuclear steam supply system is simplified, comprising: a reactor vessel (2) which integrates a reactor core (1); a first coolant (3) which is stored in the reactor vessel (2) and heated by the reactor core (1) to convect; a first heat transfer tube (4) which is arranged in the reactor vessel (2) and comes into contact with the first coolant (3); and a second coolant (5) which is supplied from the outside of the reactor vessel (2) to the first heat transfer tube (4), cools the first coolant (3) and led to the outside of the reactor vessel (2).

The invention discloses an integral low-temperature nuclear heat reactor with the circuit equipment adopting integral arrangement and belonging to the low- and medium-parameter pressurized-water reactor, wherein, a reactor core adopts the mature nuclear power plant fuel component and control rod component; a main heat exchanger is of integral coil type; a voltage stabilizer is a built-in nitrogen partial pressure control voltage stabilizer; coolant circulation is completed by a built-in jet apparatus and the equipment of an external drive circuit; the drive circuit and the equipment and a main circuit auxiliary system are arranged at the circumference of a reactor pressure vessel; a containment vessel consists of a reactor body containment vessel and a reactor top containment vessel; the reactor body containment vessel which is a structure combined by a reactor vault of reinforced concrete structure and a casing of steel structure is connected with a sealed refueling water storage pool through a pipe and a valve. The thermal power of the reactor can be selected between 50MW and 500MW at will and the outlet temperature of the reactor can be selected between 100 DEG C to 200 DEG C according to application, requirement and power.

A method of converting energy into electricity using a gaseous working fluid and an evaporative fluid comprises pressuring the working fluid (20) in a compressor (1), heating the high-pressure working fluid (22) in a recuperator (8) using thermal energy in low-pressure working fluid (34) emerging from a turbine (2), adding energy from an energy source (5, 6) to increase the temperature and enthalpy of the working fluid (32), expanding the working fluid (32) through the turbine (2), using the turbine to generate electricity, and cooling the low-pressure working fluid (34) emerging from the turbine in the recuperator. The method further comprises lowering the temperature and increasing the mass of the high-pressure working fluid (22) after leaving the compressor (1), and / or after leaving the recuperator (8), by introducing the evaporative fluid (48, 49) to produce evaporative cooling.

A light water reactor to safely convert depleted uranium into a fuel source that could be used as a sustainable source of energy for centuries. The reactor is a type of breed-burn reactor uniquely combined with a proliferation-resistant fuel cycle with no uranium enrichment and no plutonium isolation. It is comprised of a compact factory-produced fast region and a thermal region that produces about 95% of the core power and contains the passageways for transports of delayed-neutron emitters to the fast region, where they can provide additional neutrons (source-based mode) or all the necessary excitation without an external neutron source (self-regulating mode). A second embodiment of the invention is a small unit driven by a neutron source with beam recycling for propulsion, electrical power or radioisotope production. It could also serve as a demonstration facility for the transmutation reactor with fission-fusion fuel.

An In Orbit Transportation & Recovery System (IOSTAR™) (10) is disclosed. One preferred embodiment of the present invention comprises a space tug powered by a nuclear reactor (19). The IOSTAR™ includes a collapsible boom (11) connected at one end to a propellant tank (13) which stores fuel for an electric propulsion system (12). This end of the boom (11) is equipped with docking hardware (14) that is able to grasp and hold a satellite (15) and as a means to refill the tank (13). Radiator panels (16) mounted on the boom (11) dissipate heat from the reactor (19). A radiation shield (20) is situated next to the reactor (19) to protect the satellite payload (15) at the far end of the boom (11). The IOSTAR™ (10) will be capable of accomplishing rendezvous and docking maneuvers which will enable it to move spacecraft between a low Earth parking orbit and positions in higher orbits or to other locations in our Solar System.

A compact pressurised water nuclear reactor comprises a primary circuit fully integrated into the reactor vessel (10). Thus, a single steam generator (12) forms the cover of the vessel (10) and the pressuriser (30) and the primary pumps (28) are housed in the vessel (10). The same is true for the control mechanisms of the control rods (40). Finally, a venturi system (44) is also provided in the vessel (10) to create water circulation if there is a failure of the primary pumps (28).

A system and a method are provided that may be used to control the temperature of steam being reheated by a moisture separator reheater (MSR). The temperature of a steam being reheated by a MSR may be sensed, and controller embodiments may use the sensed temperature to control the transfer of heat from various MSR components into the reheated steam. By using such control embodiments, the MSR may provide optimally heated steam to other power plant components, thus increasing the performance, efficiency, and safety of a power plant.

An In Orbit Transportation & Recovery System (IOSTAR™) (10). One preferred embodiment of the present invention comprises a space tug powered by a nuclear reactor (19). The IOSTAR™ includes a collapsible boom (11) connected at one end to a propellant tank (13) which stores fuel for an electric propulsion system (12). This end of the boom (11) is equipped with docking hardware (14) that is able to grasp and hold a satellite (15) and as a means to refill the tank (13). Radiator panels (16) mounted on the boom (11) dissipate heat from the reactor (19). A radiation shield (20) is situated next to the reactor (19) to protect the satellite payload (15) at the far end of the boom (11). The IOSTAR™ (10) will be capable of accomplishing rendezvous and docking maneuvers which will enable it to move spacecraft between a low Earth parking orbit and positions in higher orbits or to other locations in our Solar System.

The invention relates to a novel architecture for a nuclear reactor of the integrated type.The invention comprises:realising the hot area and cold area separation device for the primary sodium flow in the form of two walls with cuts,providing two pumping groups hydraulically in series, one for the flow of sodium from the hot area to the cold area through the intermediate exchangers and the other in the cold area;providing outlet windows of the intermediate exchangers below the lower wall;providing outlet windows of the removal exchangers of the decay heat above the cold area, wherein all of clearances between the walls with cuts and the heat removal exchangers and the height between the two walls with cuts are previously determined so as to, during normal operation, take up differential movements between the walls, exchangers and vessel and to make it possible to establish during normal operation a thermal stratification of the primary sodium in the space defined between the horizontal portions of the two walls and so as to reduce, in case of an unexpected stop of a single pumping group, the mechanical stress applied to the walls and due to the portion of the primary sodium flow passing between said clearances.

A method of using nuclear waste material and exploiting heat generated by radioactive decay of said radioactive waste, comprising the steps of incorporating solid nuclear waste into glass, ceramic, or cementitious blocks, covering the blocks in heat absorbing sealed containers, placing the sealed containers in a columnar arrangement in a gas tight containment room, circulating a heat exchange gas around said containers, passing the heated gas through a sealed heat exchanger, and using the heated water for useful work.

The invention belongs to the technical field of nuclear reactors and discloses a heating pipe-type dual-mode space nuclear reactor core. The reactor core comprises a reactor core active zone, a reactor core cylinder, a radial reflection layer, an axial reflection layer and a control drum. The reactor core active zone is located in the reactor core cylinder. The axial reflection layer is located above the reactor core active zone. The axial reflection layer is a hollow cylindrical structure. The reactor core active zone, the axial reflection layer and a heating pipe are located in the cavity ofthe radial reflection layer. The reactor core can effectively prevent the heat pipe overheating and has the beneficial effects of safety and reliability such as passive and non-single point failure.

The invention discloses a tri-cogeneration system and a tri-cogeneration method for generating power, producing hydrogen and producing fresh water by the aid of a high-temperature gas-cooled reactor of a nuclear power plant. The tri-cogeneration system comprises a closed helium circulating system of the nuclear power plant, a superheater, a steam generator, a raw seawater pipeline, a flash evaporator, a steam ejector, a seawater desalting device, a water feeding pump, a solid oxide electrolytic tank and an auxiliary steam pipeline. The tri-cogeneration system and the tri-cogeneration method have the advantages that the circulating system of the nuclear power plant, steam electrolysis and hydrogen production processes and distillation seawater desalination processes are coupled with one another, the power is generated by the aid of a helium gas turbine at first, waste heat of partial exhaust gas of the helium gas turbine is used for electrolyzing steam and producing the hydrogen, low-temperature waste heat cooling water of a cooler is used for carrying out distillation seawater desalination by means of coupled flash evaporation and steam injection, and accordingly diversified water, power and hydrogen tri-cogeneration modes can be implemented; the electric power and the fresh water which are required for steam electrolysis and hydrogen production can be provided by means of seawater desalination and nuclear power generation, accordingly, the tri-cogeneration system is high in circulating heat efficiency and good in adjustment performance and has a good economic benefit, the reliability of equipment can be improved, environmental pollution can be reduced, the tri-cogeneration system and the tri-cogeneration method have excellent application prospects, and the like.

A method of hydraulically prestraining the tubes of a once-through steam generator by welding the tubes to their respective tubesheets prior to the application of hydraulic expansion to produce tensile stresses which shorten the tubes an equal and predetermined amount to increase the margin to buckling and increase the natural frequency of the tubes reducing flow induced vibration.

A low energy nuclear thermoelectric system for a vehicle which provides a cost-effective and sustainable means of transportation for long operation range with zero emission using an onboard low energy nuclear reaction thermal generator. The present invention generally includes a thermal generator within a thermal enclosure case, an energy conversion system linked with the thermal generator, an energy storage system linked with the energy conversion system, a cooling system and a central control system. The thermal generator reacts nickel powder with hydrogen within a reactor chamber to produce heat. The heat is then transferred to the energy conversion system to be converted into electricity for storage in the energy storage system. The cooling system provides cooling for the various components of the present invention and the control system regulates its overall operation. The present invention may be utilized to power a vehicle in an efficient, sustainable and cost-effective manner.

The invention discloses an all natural circulation-type modular small reactor. The all natural circulation-type modular small reactor comprises a reactor main body, a safe shell, a water tank and a passive safety system. The reactor main body comprises a pressure vessel. A reactor core, a direct current steam generator and a voltage stabilizer are orderly arranged in the pressure vessel from bottom to top. One end of a control rod driving mechanism matched with the reactor core is arranged at a top cover of the pressure vessel. The pressure vessel is arranged in the safe shell. The safe shellis immersed in the water tank. The passive safety system comprises a passive residual heat removal system and a passive safe shell heat transmission system. The reactor is free of forced circulation of a path of a cooling agent driven by a main pump, and utilizes density contrast of cooling agents between the direct current steam generator and the reactor core and cold and hot core potential difference to drive the cooling agents to all naturally circulate in the pressure vessel so that the reactor safety is improved. The passive safety system realizes a lasting submerged state of the reactorcore and carries out the residual heat of the reactor core to prevent core damage.

An apparatus that harnesses the thermal energy of spent fuel rods in nuclear power plants to power the cooling system of the nuclear power plant particularly the cooling for the spent fuel rod storage ponds and the main reactors. The apparatus is comprised of a heat exchanger unit that accumulates the thermal energy of the spent fuel rods, a heat conveyance system that conveys the thermal energy of the spent fuel rods, and a heat engine that receives its thermal energy input from the spent fuel rods and produces mechanical power that runs an electrical generator which powers the cooling system of the nuclear power plant, particularly the controls and pumps that cool the spent fuel rod storage ponds and the main reactors. The apparatus provides a redundant power source and makes the cooling system of nuclear power plants independent of externally supplied electrical power and thereby resolves a key redundancy and safety concern with nuclear power generation. The apparatus also has application to other industries.

The invention relates to a novel architecture for a nuclear reactor of the integrated type. The invention comprises: realising the hot area and cold area separation device for the primary sodium flow in the form of two walls with cuts, providing two pumping groups hydraulically in series, one for the flow of sodium from the hot area to the cold area through the intermediate exchangers and the other in the cold area; providing outlet windows of the intermediate exchangers below the lower wall; providing outlet windows of the removal exchangers of the decay heat above the cold area, wherein all of clearances between the walls with cuts and the heat removal exchangers and the height between the two walls with cuts are previously determined so as to, during normal operation, take up differential movements between the walls, exchangers and vessel and to make it possible to establish during normal operation a thermal stratification of the primary sodium in the space defined between the horizontal portions of the two walls and so as to reduce, in case of an unexpected stop of a single pumping group, the mechanical stress applied to the walls and due to the portion of the primary sodium flow passing between said clearances.

The subject of the present invention is to provide a nuclear reactor plant of which is a direct cycle nuclear reactor using a carbon dioxide as a coolant such that a heat evacuation for liquefying coolant is reduced while a compressive work is reduced by using a condensation capability of a carbon dioxide for enhancing a cycle efficiency.The nuclear reactor plant is comprised of a nuclear reactor 1, a turbine 2, and wherein, the coolant of supper critical state is heated by a heat of a nuclear reactor to directly drive a turbine, a gaseous coolant discharged from said turbine is chilled and compressed after said turbine is driven for keeping in a critical state, and then said coolant is circulated again into said nuclear reactor, and wherein, a carbon dioxide is used as said coolant, and a predetermined ratio of gaseous coolant discharged from said turbine is liquefied for being compressed in a liquid state while a rest of gaseous coolant is compressed in a gaseous state.

The present invention provides an inherent security pool-shell combination low temperature nuclear heating device and an operation program thereof, which belongs to nuclear energy centralized heat-supply field. The invention mainly comprises the following procedures: adopting separated layout, forced circulation and high effective small temperature difference heat exchange in primary loop of reactor; under the precondition that parameter requirements of centralized heat-supply by big cities heat supply network satisfied, reducing work temperature of shell-type heating reactor as far as possible; meanwhile optimized layout of equipment, and organic combination of normal pressure pool in large volume (47) and shell-style heating reactor(29) remove accident possibility of water loss and coldness loss of reactor core (1). Complete inherent safety principle is carried out in the invention. Thus, absolute security of nuclear heating can be guaranteed by using mature pressurized water reactor technology, and enterprises have develop nuclear station pressurized water reactor experience can possibly jump over research and develop stage and enter into nuclear heating market directly, and make a real contribution for energy-saving and emission-reduction and improving country energy structure.

A thermal / electrical power converter includes a gas turbine with an input couplable to an output of an inert gas thermal power source, a compressor including an output couplable to an input of the inert gas thermal power source, and a generator coupled to the gas turbine. The thermal / electrical power converter also includes a heat exchanger with an input coupled to an output of the gas turbine and an output coupled to an input of the compressor. The heat exchanger includes a series-coupled super-heater heat exchanger, a boiler heat exchanger and a water preheater heat exchanger. The thermal / electrical power converter also includes a reservoir tank and reservoir tank control valves configured to regulate a power output of the thermal / electrical power converter.

A reactivity control rod adapted to be used in a reactor core of a fast reactor and disposed at a substantially central portion of the reactor core for controlling a reactivity therein. The reactivity control rod includes a wrapper tube surrounded by a plurality of fuel rods in a reactor core, and a plurality of neutron absorber rods arranged in the wrapper tube. At least one of the plurality of neutron absorber rods includes a cladding tube and a mixture filled in the cladding tube. The mixture is composed of a neutron absorber that absorbs a neutron and a neutron moderator that moderates the neutron.

The invention belongs to the technical field of nuclear reactor engineering, and in particular relates to a thermally-operated conversion system which adopts lead or lead-bismuth alloy intermediate loops. The system comprises three loops; a first loop comprises a cold pool, a main pump, a reactor core, a thermal pool and an intermediate heat exchanger arranged in a main container and connected in sequence; a second loop comprises a second loop circulating pump, the intermediate heat exchanger and a steam generator connected in sequence; a third loop comprises a water supplying pump, the steam generator and a steam turbine connected in sequence; a working medium of the first loop is liquid metallic sodium, a working medium of the second loop is liquid metallic lead or a liquid lead-bismuth alloy, and the third loop is a conventional water-steam loop. By adopting the system disclosed by the invention, heat generated by the reactor core can be safely and efficiently brought out of a reactor, so that high-temperature steam is generated in the steam generator and used for pushing the steam turbine to apply work, and heat energy generated by the reactor is converted into mechanical energy.

A laser ignition / ablation propulsion system that captures the advantages of both liquid and solid propulsion. A reel system is used to move a propellant tape containing a plurality of propellant material targets through an ignition chamber. When a propellant target is in the ignition chamber, a laser beam from a laser positioned above the ignition chamber strikes the propellant target, igniting the propellant material and resulting in a thrust impulse. The propellant tape is advanced, carrying another propellant target into the ignition chamber. The propellant tape and ignition chamber are designed to ensure that each ignition event is isolated from the remaining propellant targets. Thrust and specific impulse may by precisely controlled by varying the synchronized propellant tape / laser speed. The laser ignition / ablation propulsion system may be scaled for use in small and large applications.

A method of converting energy into electricity using a gaseous working fluid and an evaporative fluid comprises pressuring the working fluid (20) in a compressor (1), heating the high-pressure working fluid (22) in a recuperator (8) using thermal energy in low-pressure working fluid (34) emerging from a turbine (2), adding energy from an energy source (5, 6) to increase the temperature and enthalpy of the working fluid (32), expanding the working fluid (32) through the turbine (2), using the turbine to generate electricity, and cooling the low-pressure working fluid (34) emerging from the turbine in the recuperator. The method further comprises lowering the temperature and increasing the mass of the high-pressure working fluid (22) after leaving the compressor (1), and / or after leaving the recuperator (8), by introducing the evaporative fluid (48, 49) to produce evaporative cooling.