Device for generating energy by means of nuclear reaction controlled to generate free neutrons

Abstract

The invention relates to a device for generating energy by means of a nuclear reaction controlled to generate free neutrons. There is disclosed a device for performing a nuclear reaction, comprising:-a source material comprising a first isotope, arranged in a first enclosure,-an ionization system configured to at least partially ionize the source material,-an ion accelerator, arranged in a second enclosure, -a first target arranged in the second shell and comprising a second isotope to allow a first nuclear reaction between the first isotope and the second isotope,-a second target arranged in the second shell or in a third shell separate from the second shell to allow a second nuclear reaction between the first isotope and the second isotope, the first isotope is a hydrogen isotope and the second isotope is a hydrogen isotope or a heavy isotope, the first nuclear reaction is a spallation reaction if the second isotope is a heavy isotope, and the first nuclear reaction is a fusion reaction if the second isotope is a hydrogen isotope.

Description

Technical Field

[0001] The present invention relates to carrying out nuclear reactions caused by the impact of an ion beam on a first target, generating neutrons which fuse with a second target, and then recovering the energy, particularly electrical energy, produced by these nuclear reactions.

[0002] The invention relates more particularly to carrying out said reactions producing neutrons starting from hydrogen isotopes, in particular the fusion of two deuterons and of a deuteron with a tritium nucleus, and also to spallation caused by projecting a hydrogen isotope, in particular protium, at a velocity greater than 0.5 GeV onto a heavy isotope, in particular mercury or tungsten.

[0003] The present invention can also be used to generate tritium.

[0004] In the context of the present invention, "nuclear fusion" means the process by which two atomic nuclei are combined to form a heavier atomic nucleus. This is in particular different from spallation, in which a nucleus struck by an incident particle breaks apart as a result of the impact. "Nuclear reaction" means a process by which the composition of a nucleus changes, for example by fusion, by fission, by spallation or by absorption of neutrons.

[0005] In the context of the present invention, "heavy isotope" means an element whose density in liquid or solid form is greater than or equal to 12 g / cm 3 isotopes. Background Art

[0006] Currently, atomic energy is mainly produced through nuclear fission reactions, which result in the production of many unstable isotopes with potentially very long half-lives.

[0007] In addition, nuclear fission reactors often require considerable time (e.g., several days) to shut down. During this period of shutdown, cooling may be necessary to prevent the still very active fission products from initiating a chain reaction.

[0008] Nuclear fusion is currently used especially in the context of atomic weapons (in this case in combination with nuclear fission reactions), and requires very high temperatures and pressures to collide atomic nuclei in order to cause fusion of these nuclei.

[0009] Therefore, it is difficult to control the reaction of nuclear fusion.Now, nuclear fusion represents a potential clean and abundant energy source.

[0010] It is known to induce fusion of deuterium nuclei by subjecting them to a high voltage of about 40 kV in a vacuum chamber. However, this method does not allow the recovery of the energy produced by the fusion of isotopes, or even the recovery of neutrons using elements that absorb them.

[0011] Application EP 2561514 A1 discloses a hybrid reactor, i.e. a nuclear fission reactor driven by a particle accelerator. According to the method described in the application, a proton flux is directed to a target to cause nuclear spallation of the target and thus generate neutrons for controlling the activity of the nuclear reactor core. Although the application involves the use of accelerated particles to cause nuclear spallation, it does not disclose a nuclear fusion process.

[0012] It is therefore necessary to propose a device for carrying out nuclear reactions which allows the recovery of the energy released by these reactions and which does not require subjecting the reactants to conditions of high temperature and pressure. It is also necessary to propose a device for the production of tritium.

[0013] It is an object of the present invention to at least partially respond to these needs. Summary of the invention

[0014] For this purpose, according to one aspect of the invention, the invention relates to an apparatus for carrying out a nuclear reaction, comprising:

[0015] - a source material comprising a first isotope, arranged in a first enclosure,

[0016] - an ionization system configured to at least partially ionize the source material,

[0017] an ion accelerator configured to accelerate ions originating from the source material to a first target arranged in a second enclosure and containing a second isotope so as to allow a first nuclear reaction between the first isotope and the second isotope,

[0018] - a second target, arranged in the second enclosure or in a third enclosure separate from the second enclosure, to allow neutrons produced by the first nuclear reaction to react with nuclei of atoms of the second target,

[0019] the first isotope is a hydrogen isotope and the second isotope is a hydrogen isotope or a heavy isotope,

[0020] If the second isotope is a heavy isotope, the first nuclear reaction is a spallation reaction; if the second isotope is a hydrogen isotope, the first nuclear reaction is a fusion reaction.

[0021] If the second isotope is a heavy isotope, it is selected in such a way that its nuclear reaction with the first isotope produces one or more neutrons. The heavy isotope may be selected in particular from the isotopes listed in Table 1, in particular xenon 132, mercury 202, tantalum 181, lead 208, platinum 194, 195 or 196, iridium 193, osmium 190, tungsten 184 or 186, hafnium 178 or 180, ytterbium 174, erbium 168, dysprosium 162 or 164, or barium 138.

[0022] [Table 1]

[0023]

[0024]

[0025] Thus, according to a variant of the invention, the device according to the invention makes it possible to ionize a first hydrogen isotope and accelerate the ions produced towards a second hydrogen isotope constituting a first target, thereby obtaining a nuclear fusion reaction between the first isotope and the second isotope. This fusion produces free neutrons according to one of the following reactions, in which D stands for deuterium, T stands for tritium, n stands for neutrons, and eV energy is in electron volts, in particular released in the form of kinetic energy of the neutrons:

[0026] D+D→n+ 3 He + 3.30 MeV, or

[0027] D+T→n+ 4 He+14.1MeV.

[0028] According to a second variant of the invention, the device according to the invention makes it possible to ionize a first hydrogen isotope, such as protium, and to accelerate the ions produced towards a heavy isotope constituting a first target, such as mercury or tungsten, in order to obtain the spallation of the neutrons of the target isotope. Each nucleus of the first isotope advantageously allows the release of several neutrons from the heavy isotope.

[0029] Neutrons generated by the first nuclear reaction and optionally slowed down cause a second nuclear reaction with a second target. The second target can advantageously consist of isotopes of hydrogen or many other elements, in particular boron 10, helium 3, lithium 6, nickel 58, nickel 60, tungsten 182, boron oxide B2O3 with a boiling point of 1860°C and chemical stability, sodium tetraborate Na2B4O7 with a melting point of 700°C and chemical stability, and boron nitride BN with a melting point of 2967°C, B being boron 10. The second target can act as a moderator or can be separated from the moderator. However, in the latter case, the moderator will react nuclearly with the neutrons like the target material, but in a smaller proportion, especially if the material constituting the second target has a larger absorption cross section than the moderator.

[0030] If the target material is separate from the moderator, the moderator is advantageously dispersed therein (e.g., in the form of beads or in the form of a mixture) to utilize neutrons slowed therein, and also dispersed at the periphery of the second enclosure or the third enclosure to capture slow neutrons circulating therein and prevent them from escaping from the enclosure. Alternatively, neutrons generated by the first nuclear reaction are slowed in a moderator arranged in or around the second enclosure.

[0031] Speed ​​reducer

[0032] The moderator advantageously contains elements of low atomic number and high elastic effective cross section, in particular dihydrogen, helium 4, argon 36, methane, water, polystyrene with a boiling point of 806° C., calcium hydride CaH2 with a melting point of 816° C., sodium hydroxide NaOH with a boiling point of 1388° C. and chemical stability, potassium hydroxide KOH with a boiling point of 1327° C. and chemical stability. These elements can be in gaseous state (preferably under pressure), in liquid or solid form or in a supercritical state.

[0033] Alternatively or in combination, the second target is mixed with a moderator or acts as a moderator. Thus, the second target can be mixed with helium 4, argon 36, methane, water, polystyrene, calcium hydride CaH2, sodium hydroxide NaOH, potassium hydroxide KOH, or it can advantageously consist of helium 3, heavy methane CD4, heavy water D2O, heavy polystyrene (C8D8) n , calcium deuteride CaD2, sodium deuteride NaOD, potassium deuteride KOD, dihydrogen borate H2BO3, dihydrogen borate D2BO3, decaborane B 10 H 14 , heavy decaborane B 10 D 14 , calcium deuteride CaD2 or the hydrogenated compounds as mentioned above, wherein some of the hydrogen atoms are replaced by deuterium or tritium atoms.

[0034] Alternatively, the apparatus does not contain a moderator and the target material is preferably contained within a housing having a thickness of 1 meter to 70 meters.

[0035] Target material

[0036] The target material selected is preferably an element whose reaction products with neutrons are nuclear stable and have a large neutron absorption cross section, which is abundant and preferably can be easily separated from other isotopes of the same element with smaller absorption cross sections. Target materials are, for example, helium 3, boron 10, lithium 6, calcium 40, tungsten 183, xenon 130 or 131, platinum 196, mercury 201, titanium 148, cadmium 111, iron 56, nickel 58, nickel 60 or nickel 62, sulfur 32, sodium 23, zinc 64, zinc 66 or zinc 68 or nitrogen 14. Preferred target materials can be mixed with other target materials, preferably selected so that they are stable with fusion products of neutrons.

[0037] The energy generated can be recovered in the form of heat, chemical or electricity.

[0038] In a preferred embodiment, the apparatus according to the invention is used to generate electricity, some of which is used to accelerate ions of a target material.

[0039] According to an advantageous variant, the device is also used to generate tritium. Tritium is an unstable isotope of hydrogen, but advantageously allows very energetic fusion reactions, in particular with protium, and can participate in the first nuclear reaction of the device described in this application.

[0040] For example, tritium can be produced by one of the following reactions:

[0041] 14 N+n→ 12 C+T

[0042] 6 Li+n→ 4 He+T

[0043] n+D→T.

[0044] The device according to the invention may also include one or more of the following optional features:

[0045] - The ionization system comprises a laser and an input waveguide configured to direct light emitted by the laser towards an optical input of the first housing, the optical input configured to allow the emitted light to illuminate the source material.

[0046] The ionization system comprises an X-ray emission system arranged in the first housing so as to at least partially ionize the source material.

[0047] The ion accelerator comprises a high voltage generator electrically connected to a first electrode and a second electrode, the first electrode and the second electrode being arranged in a second housing, the generator and the first electrode and the second electrode being configured to generate an electric field for accelerating ions from a source material to a first target, thereby causing fusion of nuclei of the ions from the source material with nuclei of the first target.

[0048] At least the first housing and / or the second housing is surrounded by a wall which contains a material which absorbs gamma rays, for example tungsten or lead.

[0049] - The second target is arranged in a third housing, the third housing being arranged around the second housing.

[0050] The device comprises a cooling circuit in which a cooling fluid circulates at least partially in the wall of the second housing and / or in the wall of the third housing.

[0051] -The device comprises a system for recovering thermal energy released by slowing down ions accelerated onto a first target and / or by a first nuclear reaction and / or by slowing down neutrons and / or by a fusion reaction of neutrons with a second target. The energy recovery system comprises, for example, a gas under pressure in a housing arranged to recover at least part of the released heat to increase the pressure of the gas. The housing may comprise a valve allowing the gas to expand to cause a turbine to rotate for power generation. The energy recovery system may alternatively or in combination comprise a chemical reactor arranged to recover at least part of the released heat and in which an endothermic chemical reaction occurs, for example enabling the formation of dihydrogen or supplying a battery or fuel cell as described below.

[0052] The device comprises a gamma-ray absorbing material arranged in or around the third enclosure such that it absorbs more than 50%, more than 80%, more than 90% or more than 99% of the gamma-rays generated in the third enclosure.

[0053] - The first isotope and the second isotope are selected from deuterium and tritium, only one of which may be tritium.

[0054] - The device comprises one or more coils surrounding the accelerated ion beam, acting as magnetic lenses for focusing the ion beam or keeping it focused.

[0055] - The first isotope is deuterium in gaseous form, the deuterium circulates in a loop comprising a first enclosure, the loop being configured to cool the deuterium.

[0056] The second target comprises lithium-6, preferably consists of lithium-6.

[0057] - The first enclosure preferably comprises a gas inlet and a gas outlet configured to allow the first isotope to circulate in the first enclosure.

[0058] - The inner wall of the first housing is at least partially covered with a dielectric material.

[0059] - The inner wall of the second housing is preferably at least partially covered with a dielectric material.

[0060] The wall of the second housing and / or the wall of the third housing is penetrated by one or more liquid coolants.

[0061] The present invention also relates to but is not limited to:

[0062] - Use of the device according to the invention as a chemical reactor for heating a chemical product, allowing a chemical reaction, in particular an endothermic reaction, to take place with or without a catalyst. The chemical product preferably circulates in the walls of the second enclosure and / or of the third enclosure to ensure its cooling, and / or in the enclosure itself. The chemical product is then heated in particular by slowing down the heat transfer generated by ions and by absorbing gamma rays from nuclear reactions, and if it is located in the third enclosure or in the walls of the second enclosure, by slowing down the neutrons released from the second enclosure, reacting with said neutrons, preferably also by nuclear reactions;

[0063] - use of the device according to the invention for producing hydrogen by pyrolysis, in particular starting from a sulphur-iodine cycle supplied by heat recovered from a heat-conducting material or, for example, by a similar cycle in which iodine is replaced by another halogen, such as bromine or chlorine;

[0064] - the use of the equipment for the generation of electricity;

[0065] - the purpose of the equipment for heating water or steam;

[0066] - Use of the device for regenerating zinc dioxide into zinc and oxygen;

[0067] - Use of a device for supplying heat to a power plant by regeneration of electrodes and / or supporters of combustion and / or fuels and / or electrolytes, in particular as described in patent application numbered FR 2110637 and entitled “Fuel cell system” filed on October 7, 2021; none or at least one of the endothermic chemical reactions necessary for the process takes place at least partially in one of the casings of the nuclear device or in one of the cooling circuits.

[0068] If the liquid coolant is the site of the nuclear reaction, in particular if it circulates in the wall of the second enclosure or in a third enclosure, the device preferably includes means, such as valves, allowing the discharge of gaseous elements newly produced or resulting from possible degradation of unstable isotopes occurring after fusion of the liquid coolant with neutrons. BRIEF DESCRIPTION OF THE DRAWINGS

[0069] [ Figure 1 ] Figure 1 A first embodiment of the device according to the invention is shown.

[0070] [ Figure 2 ] Figure 2 A second embodiment of the device according to the invention is shown.

[0071] [ Figure 3 ] Figure 3A third embodiment of the device according to the invention is shown.

[0072] [ Figure 4 ] Figure 4 An assembly is shown including an ionization system and an ion accelerator.

[0073] [ Figure 5 ] Figure 5 yes Figure 4 Detailed view of the components in the . DETAILED DESCRIPTION

[0074] Figure 1 A device 1 according to the invention is shown which is configured to produce tritium at moderate temperatures, ie at temperatures between 200°C and 400°C.

[0075] The apparatus 1 comprises an assembly 100 of an ionization system and an ion accelerator, which is Figure 4 The assembly 100 allows for the generation and acceleration of ions of a first hydrogen isotope, in this example deuterium.

[0076] Ions of the first isotope are injected into a supply channel 101 leading to a second housing 102 containing a first target 103. The channel 101 is advantageously angled to reach the second housing 102, the trajectory of the ions being bent under the effect of a magnetic field generated by a magnet or coil (not shown) to follow the curve in the channel. The supply channel has a spiral shape (not shown) for its portion contained in the housing 109 for absorbing neutrons, the rotation of the ions being provided by the presence of a magnetic field generated by a solenoid 122 surrounding said channel in this portion.

[0077] The first target 103 in this embodiment is deuterium in gaseous form. The gaseous deuterium may be introduced from a source 104 into the second housing via a channel 105. Advantageously, the channel 105 also has a helical shape insofar as its portion contained within the housing 109 (not shown).

[0078] The second housing 102 is arranged in a third housing 109. The third housing 109 contains a second target 110, which in this embodiment is liquid lithium 6. Lithium 6 can be introduced into the third housing via a channel 111. Preferably, an intermediate housing is arranged around the second housing 102, in the third housing 109. The intermediate housing contains a moderator, preferably liquid water or water in a supercritical state, argon 36 or supercritical dihydrogen. The thickness of the moderator in the intermediate housing is advantageously 5 cm to 20 cm, and the thickness of the lithium 6 in the third housing is advantageously 1 cm to 2 cm. The use of an intermediate housing containing a moderator can significantly reduce the required volume of lithium 6.

[0079] Advantageously, the intermediate housing is cooled.

[0080] Preferably, a membrane 106 permeable to ions of the first isotope but impermeable to the first target contained in the second housing 102 is arranged at the ion inlet of the second housing 102. The membrane 106 is composed, for example, of six layers of graphene, graphane or hexagonal boron nitride so that the first target 103 causes little or no delay of the ions during their acceleration or transport through the devices 100 and 101.

[0081] More preferably, the wall 113 of the second enclosure 102 comprises a heat-resistant material that absorbs little neutrons, such as iron or an iron alloy, and is covered with a dielectric material, such as glass, so that electrons are not stripped from the wall by deuterium ions originating from the device 101 .

[0082] Advantageously, one or more electrodes 107 including a cathode 108 are arranged in the second housing in order to accelerate the ions of the first isotope, in particular to compensate the friction of these ions in the first target material by the Bragg effect. These electrodes, except for the cathode 108, are preferably covered with a dielectric material, such as mica or silicon dioxide, to prevent electrons from being stripped from them. In the context of the present invention, these electrodes are called maintenance electrodes (maintenance electrodes).

[0083] The apparatus is configured so that ions of the first isotope have sufficient velocity in the second enclosure 102 to cause a nuclear fusion reaction with the first target 103. The deuterium ions preferably have an energy of 30 MeV to 80 MeV, for example 50 MeV if there is no maintenance electrode, or 750 KeV to 15 MeV if there is a maintenance electrode; for example 10 MeV.

[0084] Two deuterium nuclei fuse to produce helium-3 3 He and neutrons.

[0085] The energy generated by the first fusion reaction is in the form of kinetic energy of the reaction products, i.e. neutrons and helium. This kinetic energy, and in particular the kinetic energy of the helium, together with the heating of the first target gas by the Bragg effect due to the transport of ions in the gas, contributes to a significant heating of the first target gas contained in the second enclosure.

[0086] The kinetic energy of the helium-3 helps heat the gaseous deuterium in the first target.

[0087] The neutrons produced by the first fusion reaction have a high speed that is substantially directed in the direction of the deuterium ion beam. Therefore, the neutrons produced advantageously do not enter the channel 105 once produced. However, they may enter therein due to rebounding on the nuclei of the first target element and the second target element.

[0088] Advantageously, the lithium 6 contained in the third enclosure 109 makes it possible to moderate the temperature within the second enclosure 102 .

[0089] The generated helium 3 can be separated from the gaseous deuterium by a separator 114 known per se. The separator 114 can be operated, for example, by oxidizing deuterium to form heavy water, followed by electrolysis to produce deuterium. In addition, the separator 114 is also arranged to cool or collect heat from the deuterium / helium 3 mixture.

[0090] The neutrons produced by the first nuclear fusion reaction are slowed down in a moderator and then react with lithium-6 nuclei to form gaseous helium-4 4 He and tritium. Since lithium 6 has a high boiling point, a plurality of sub-compartments may be arranged in the third housing 109 and cooled to different temperatures.

[0091] Preferably, a gas deflector 112 is arranged below the housing containing the moderator to prevent accumulation of tritium and helium 4 that may circulate in the liquid lithium 6.

[0092] Helium 4 and gaseous tritium can be discharged from the third housing 109 via a channel 115. The channel 115 conveys the gas mixture to a second separator 116, which is configured to separate helium 4 from tritium, for example, by oxidation of tritium. Preferably, the channel 115 conveys the gas mixture to a cooling circuit 117, which is configured to cool the gas mixture before being introduced into the second separator 116.

[0093] More preferably, the third enclosure 109 is configured to limit gas accumulation in the upper part of the third enclosure. The top of the enclosure may, for example, have the shape of an inverted funnel (not shown), from which the gas mixture of tritium and helium 4 enters the conduit 115.

[0094] Advantageously, the lithium 6 may be cooled by circulation in a lithium cooling loop 118 .

[0095] During operation of the device, the temperature of the lithium 6 is advantageously maintained between 200° C. and 400° C. If the temperature of the lithium approaches its boiling point, a temperature controller or a fuse (not shown) may advantageously be inserted to stop the electrical acceleration of the ions.

[0096] Preferably, the third housing 109 is arranged in a fourth housing 119 containing lead. Lead is able to absorb the gamma radiation generated in the third housing. The lead is preferably kept at a temperature of about 400° C. in a liquid state. It can then circulate in a lead cooling circuit 120, which allows its heat to be recovered. This makes it possible to generate energy, for example by means of a steam turbine, some of which is used to provide energy to an ion generator and an accelerator. Alternatively, the device is configured so that the lead remains in a solid state. Channels for circulation can then be arranged in the lead, in which a heat transfer fluid circulates. The walls of the housings 109 and 121 are made, for example, of stainless steel.

[0097] The wall 121 of the fourth enclosure 119 advantageously comprises a thermal protection that reflects heat (i.e. infrared radiation). Such protection consists, for example, of a Bragg mirror, such as a device known under the name "thermal mirror". The wall 121 may also contain one or more plates of neutron absorbing material (e.g. boron 10), for example a boron 10 plate with a thickness of 3 cm, which can absorb neutrons that are not absorbed by the lithium 6.

[0098] Figure 2 A second embodiment of a device 1 ′ according to the invention is shown, which is configured for producing tritium at high temperature, ie at a temperature above 1000° C., for example 1100° C. Figure 2 Device 1' in Figure 1 The device 1 in FIG. 1 differs specifically in the way it generates electricity from heat.

[0099] Part of the structure of the device 1' is similar to Figure 1 The device 1 is shown. For the sake of clarity, identical elements are identified with the same reference numerals.

[0100] Therefore, if Figure 1 In the embodiment shown, the apparatus 1' comprises an assembly 100 comprising an ionization system and an ion accelerator. The first isotope ionized by the ionization system is deuterium.

[0101] Deuterium ions are delivered via a supply channel 101 to a second housing 102 containing a first target 103. The supply channel 101 advantageously has a spiral shape (not shown) insofar as its portion is comprised in a neutron absorbing housing 109, the rotation of the ions being provided by the presence of a magnetic field generated by a solenoid. This spiral shape allows neutrons penetrating into the vacuum of the channel to travel only no further than a portion of the spiral, whereas some neutrons could pass through the entire channel if the latter were rectilinear, thereby escaping from the device. In this embodiment, the first target 103 is deuterium in gaseous form. Gaseous deuterium can be introduced into the second housing from a source 104 via a channel 105. Advantageously, the portion of the channel 105 comprised in the housing 109 also has a spiral shape (not shown).

[0102] The second housing 102 is arranged in a third housing 109. The third housing 109 contains a second target 110, which contains liquid lithium 6. The lithium 6 can be introduced into the third housing 109 via a channel 111.

[0103] If an intermediate enclosure between the second and third enclosures is used, a moderator, such as water, dihydrogen or argon 36 at supercritical pressure, may be introduced therein and lithium 6 introduced into the third enclosure.

[0104] The apparatus is configured so that the ions of the first isotope have sufficient velocity in the second enclosure 102 to cause a nuclear fusion reaction with the first target 103. The deuterium ions may, for example, have an energy of 30 MeV to 50 MeV.

[0105] The fusion of two deuterium nuclei produces helium-3 and neutrons.

[0106] The neutrons produced by the first fusion reaction have a high velocity that is substantially directed in the direction of the deuterium ion beam.

[0107] The generated helium 3 can be separated from the gaseous deuterium by the separator 114 .

[0108] The neutrons produced by the first nuclear fusion reaction have enough kinetic energy to react with lithium-6 nuclei to form gaseous helium-4 4 He and tritium.

[0109] Advantageously, the apparatus is configured so that during operation, the lithium 6 reaches a temperature above 600° C., allowing tritium to react with lithium, for example 1100° C. In addition, a small amount of carbon, for example 10 ppm to 50 ppm, preferably 20 ppm, may be introduced into the lithium 6. Thus, when the temperature of the lithium 6 is increased and the carbon acts as a catalyst, tritium may chemically react with lithium to form LiT.

[0110] The gaseous helium 4 may be exhausted from the third housing 109 via a passage 115 arranged in an upper portion of the housing 109 .

[0111] Advantageously, the lithium 6 may be cooled by circulation in a lithium cooling loop 118 .

[0112] Once cooled, LiT and 6 The mixture of Li is decanted into the decanter 130. In fact, LiT is denser than liquid lithium 6. Therefore, LiT and lithium 6 can be separated.

[0113] Advantageously, decanter 130 may be replaced with a centrifuge configured to separate LiT and lithium 6 by centrifugation.

[0114] Alternatively, the separation can be carried out at a temperature greater than or equal to 1100° C.: LiT is gaseous, while lithium 6 is liquid, and can therefore be separated by gas evolution.

[0115] The collected lithium 6 may then be reinjected into the third enclosure 109 via the channel 131 .

[0116] The collected LiT is injected into a reactor containing sulfur dioxide 132. LiT reacts with the latter to form lithium sulfate Li2SO4 and ditritium.

[0117] The tritium can then be discharged from the device.

[0118] The lithium sulphate is advantageously injected into the electrolytic cell 134 via the channel 133. The electrolysis allows the sulphur dioxide to be separated from the lithium 6 which can be reinjected into the third enclosure 109.

[0119] Preferably, the third housing 109 is arranged in a fourth housing 119 containing lead with a boiling point of 1749°C. Preferably, the walls of the fourth housing 119 are formed of a metal that remains solid at the temperature of the lead and lithium in the device, such as stainless steel containing 16% chromium or tungsten. The lead can absorb the gamma radiation generated in the third housing. When heated sufficiently, the lead becomes liquid. It can then circulate in the lead cooling circuit 120, allowing heat to be recovered therefrom. Alternatively, the device is configured so that the lead remains solid. Channels for circulation can then be arranged in the lead, in which a heat transfer fluid circulates.

[0120] The wall 121 of the fourth housing 119 advantageously comprises a thermal protection which reflects heat.

[0121] The equipment for heat recovery and for cooling is advantageously an equipment allowing the latter to be converted into electricity, as described in the patent application numbered FR 2110637 and entitled “Fuel cell system” filed on October 7, 2021. It is then possible to use conversion methods using heat at temperatures of 1100° C. or lower, in particular:

[0122] - Using zinc-air batteries, the conversion efficiency can be close to 89% by regenerating zinc from zinc oxide by adding hydrogen at 1100°C,

[0123] - Using zinc-air batteries, the conversion efficiency can approach 100% by regenerating zinc from zinc oxide through oxidation with carbon monoxide at 880°C.

[0124] - Or use sodium / manganese oxide batteries, which use electrolysis of carbon dioxide at high temperatures (above 750°C) to regenerate electrodes and fuels, and their conversion efficiency can be close to 100%.

[0125] Some or all of the electricity generated may be used to generate ions toward and accelerate the ions in the first target.

[0126] Figure 3 A third embodiment of a device 1 ″ according to the invention is shown, which is configured for regenerating zinc oxide into zinc.

[0127] The apparatus 1 ″ comprises an assembly 100 including an ionization system and an ion accelerator configured for ionizing source isotopes and accelerating the obtained ions.

[0128] Preferably, the source isotope in this embodiment is deuterium.

[0129] Deuterium ions are guided into a second housing 102 via a channel 101. The supply channel 101 advantageously has a helical shape (not shown) for its portion comprised in a neutron absorbing housing 109, the rotation of the ions being provided by the presence of a magnetic field generated by a solenoid. The housing 102 contains a first target 103 in the form of gaseous ditritium.

[0130] Advantageously, an electrode assembly comprising an anode 140, a cathode 108 and a maintenance electrode 107 is arranged in the second enclosure 102 and is configured for accelerating the ions introduced into the second enclosure and / or for keeping the velocity of the ions in the second enclosure constant by generating an electric field. If the tritium is at a pressure of 1 atmosphere, the value of the electric field may be 500 000 to 5 000 000 V / m, preferably about 1 million volts per meter.

[0131] A membrane 106 , preferably permeable to ions but impermeable to gaseous ditritium, is arranged in the second housing 102 , advantageously between the entry point of the channel 101 into the second housing 102 and the electrodes 140 , 108 , 107 .

[0132] In a preferred embodiment, the membrane 106 also constitutes the anode 140 .

[0133] Advantageously, the solenoid 141 is arranged along the conduit 101 and generates a magnetic field suitable for directing the ion beam in the conduit 101 and keeping the ion beam narrow in the conduit 101 .

[0134] The deuterium ions are accelerated to sufficient speed to undergo a nuclear fusion reaction with a tritium target contained in a second enclosure. The fusion reaction produces helium-4 and neutrons.

[0135] Tritium can be injected into the second housing 102 via the inlet channel 145. The outlet channel 146 advantageously enables the discharge of tritium, generated helium and deuterium ions that have not yet fused with tritium. Advantageously, the channel 145 and the portion of the channel 146 contained in the housing 109 also have a spiral shape (not shown).

[0136] Preferably, outlet passage 146 leads to a separator (not shown) configured to separate helium from tritium and deuterium. The separator may, for example, cause deuterium and tritium to react with an oxidant. The separator preferably also includes a mechanism for cooling ditritium, which has been heated by slowing down deuterium ions, also allowing heat energy to be recycled.

[0137] The energy of the ions may be approximately 45 MeV.

[0138] Neutrons generated in the second enclosure 102 are absorbed, in particular in the third enclosure 109. The neutrons undergo nuclear reactions with the material through which they pass, and in particular with the material contained in the enclosure 109. Calcium hydride under pressure, with hydrogen used as a moderator, calcium melted at 816° C. as a target material, or sodium hydroxide is preferably selected as the material contained in the enclosure 109. This material is maintained at a temperature of 2000° C., causing the reduction of zinc oxide.

[0139] Alternatively, the housing 109 may contain a gas such as Helium 3, which is both a moderator and a target, preferably at high pressure, for example about 10 atmospheres. This requires a Helium 3 thickness of about 0.15 m. Preferably, an intermediate housing is arranged in a third housing surrounding the second housing, the intermediate housing containing the moderator. However, if the target material is boric acid or metaboric acid, preferably in a liquid phase, it is preferred that no intermediate housing is used.

[0140] The heat generated by the Bragg effect in the second housing 102 is advantageously discharged through a circuit (not shown) for cooling ditritium and / or through the circulation of tin in a tin cooling circuit 143 arranged at least partially around the second housing 102. The circulation of tin (when the tin is heated to a temperature sufficient for liquefaction) is preferably provided by a pump 144.

[0141] The tin circulating in the loop 143 also has the function of absorbing neutrons and gamma rays.

[0142] The second housing 102 and the third housing 109 are arranged in a fourth housing 148. The fourth housing 148 includes an orifice 147 configured to allow passage through for supply and discharge of material. Preferably, the orifice 147 is arranged in the lower part of the device 1 "so that the nuclear reactions occurring in the second housing and the third housing do not generate radiation that can pass through the orifice 147.

[0143] The fourth enclosure 148 advantageously contains zinc oxide powder ZnO and is configured to provide protection against gamma radiation generated by the nuclear reactions occurring in the second enclosure and the third enclosure.

[0144] Advantageously, zinc oxide absorbs gamma radiation that is not absorbed by the neutron absorbing material. In addition, heat recovered by absorbing gamma rays can be recovered by the reaction ZnO→Zn+ at 1975°C at one atmosphere of pressure. 1 / 2O2 is converted into chemical energy.

[0145] Zinc oxide can be introduced into the fourth housing 148 through the worm 149. Zinc in a gaseous state at a temperature above 1727° C. and dioxygen generated in the fourth housing 148 are discharged via a discharge line 150. For example, dioxygen can be separated from zinc by bringing the gas mixture to a certain pressure (the partial pressure of gaseous zinc reaches a pressure at which the gaseous zinc becomes liquid, i.e., a pressure above 30 GPa).

[0146] Advantageously, the zinc oxide powder is compacted in the fourth housing, for example by means of a screw and a piston, in order to reduce its consumption.

[0147] Preferably, a loop of heat transfer metal, such as tin 143, may be arranged in the fourth housing 148 and around the second housing 102, preferably surrounded by a stainless steel tube for cooling the housing 102. The metal is then subjected to a nuclear reaction with the protons originating from the housing 102.

[0148] If the tin contains the tin isotope 112, the circuit of tin 143 is preferably protected externally from ultraviolet radiation due to degradation of the tin to indium.

[0149] If the tin contains isotopes 113, 121 and / or 123, trace amounts of indium and antimony may be present in the tin circuit 143. These trace amounts can be separated by heating the tin, the boiling points of indium and antimony being lower than that of tin.

[0150] Advantageously, the second enclosure 102 and the third enclosure 109 are at least partially separated by a space 151 in which an at least partial vacuum is maintained. This makes it possible to advantageously increase the volume of neutron-absorbing material and gamma-ray-absorbing material in order to reduce the thermal energy density and thus give the device greater thermal inertia in the event of a failure or malfunction of the cooling device.

[0151] More advantageously, the third enclosure 109 and the fourth enclosure 148 are at least partially separated by a space 152 in which an at least partial vacuum is maintained. The space 152 is configured as a region protected from neutrons, from which no gamma rays are generated, and in which the orifice 147 can be arranged in an axis that is not irradiated by gamma rays originating in particular from the elements 102, 43, 109 and 101. In particular, the orifice 147 is preferably not aligned with the device 109.

[0152] Preferably, a heat reflective wall 153 (eg comprising a Bragg mirror, such as a thermal mirror) for heat protection, advantageously having low thermal conductivity, is arranged around the fourth housing 148 .

[0153] Figure 4 An assembly 100 is shown comprising an ionization system and an ion accelerator as used in a device according to the invention.

[0154] In the embodiment shown, the assembly 100 comprises a laser 2, a reinsertion circuit 3 and a first enclosure 9. The light generated by the laser 2 (optionally amplified in the reinsertion circuit 3) is used to ionize a source isotope contained in the first enclosure 9.

[0155] The assembly 100 further comprises an anode 4 and a cathode 6 , preferably arranged at opposite ends of the first housing 9 , and a high voltage generator 10 .

[0156] The housing 9 may include a membrane 5 which is permeable to the ionized isotopes but impermeable to the isotopes in gaseous form, so as to prevent the passage of the source gas in the acceleration channel.

[0157] Ionization of the source isotope occurs in the electric field generated by electrodes 4 and 6. The generated ions are accelerated by the electric field.

[0158] If the ions are generated outside an electric field, they are surrounded by electrons produced by the ionization process, thus ensuring overall electrical neutrality.

[0159] In order to avoid the accumulation of slow ions, the electric field in the ionization region is preferably selected to be sufficiently high while remaining below a value that would cause breakdown of the source isotope gas. The electric field may, for example, have a value of 4000 to 4500 V / m, and the source isotope may be ionized over a considerable thickness, especially with a large cross section of ionizing light.

[0160] To accelerate the ions of the source isotope sufficiently to allow fusion of the ions with the nucleus of the first target, the voltage generated by the generator 10 may be between 30 000 V and 80 000 000 V. The generator 10 consists, for example, of generators mounted in series sold under the name Perseus by the company Genvolt.

[0161] The anode 4 is preferably placed in the compartment containing the source element to be ionized. The anode 4 is electrically conductive, which allows it to conduct and discharge the electrons produced by the ionization of the source isotope. The cathode is preferably covered with a dielectric layer to prevent electrons from being stripped from it.

[0162] Advantageously, a coil 8 configured to generate a magnetic field (preferably 0.1 T to 10 T, for example 0.2 T) is arranged around the housing 9 along an axis parallel to the electric field generated between the electrodes 4 and 6 and tends to keep the ions of the source isotope in the axis of the coil. The coil 8 is advantageously centered on an axis passing through the intersection of the path of the light generated by the laser 2 and the axis of the electric field between the electrodes 4 and 6.

[0163] Therefore, the first isotope in the first enclosure is preferably surrounded by a coil 8 configured to generate a magnetic field. This magnetic field makes it possible to prevent the ionized isotope from moving longitudinally in directions other than the acceleration direction defined by the electric field generated by the generator 10 between the electrodes 4 and 6. This limits the contact of the ionized isotope with the enclosure wall while keeping the ionized isotope close to the electric field axis.

[0164] exist Figure 5 In an embodiment, the first shell preferably includes a membrane that is permeable to ionized isotopes but impermeable to isotopes in gaseous form so as to prevent the source isotopes from passing through the acceleration field. It can be a component of a six-layer hexagonal boron nitride as known in the literature "Vapor-liquid-solid growth of large-area multilayer hexagonal boron nitride on dielectric substrates", Z. Shi et al., Nature communications, 11 (1), 1-8, 2020 and "LargeArea Monolayer Hexagonal Boron Nitride on Pt foil", JH Park et al., Acs Nano, 8 (8), 8520-8528, 2014.

[0165] The position of the membrane is chosen in such a way that the value of the electric field at the membrane level is below the breakdown threshold of the first isotope in the gaseous state. This threshold depends on the gas pressure and can be evaluated using Paschen's law.

[0166] The ions of the first isotope are then accelerated by the electric field generated by the generator 10. When the ionized isotopes generate a radial electric field (i.e., orthogonal to the axis of the accelerating field), some of the ionized isotopes may be deflected toward the outside of the accelerating field. In this case, it is advantageous to provide a solenoid around the first housing, the solenoid being configured to generate a magnetic field that tends to keep the ionized isotopes in the axis of the solenoid, which may coincide with the axis of the first housing. The generated magnetic field may be, for example, 0.1 T to 10 T.

[0167] Calculations performed by the inventors show that the deviation of the ionized isotopes due to the electric field generated by the ionized isotopes may be small, depending on the configuration of the device and in particular due to the influence of the magnetic field generated by the coil or coils.

[0168] The first isotope can be introduced into the first housing by means of a pressure reducing valve. However, when the first isotope is in a gaseous state and ionized at a rate that does not allow its uniform replacement, or in order to prevent the generation of ions at an insufficient distance from the anode, or in order to concentrate the generation of ions between electrodes 4 and 6, the source gas is preferably introduced into the housing via a first tube, the end of the first tube opening into the first housing forming a nozzle. The gas is then preferably sucked toward a second tube arranged in the axis of the nozzle of the first tube. The end of the second tube opening into the first housing is preferably formed as a funnel. However, the entrance of the ion acceleration line is preferably close to the intersection of the gas jet and the path of the light originating from the optical input in the first housing.

[0169] The first and second tubes are preferably fluidly connected to a pump to force the gas to circulate in the tubes, and to a gas reserve for injecting the gas into the first housing as the gas is consumed (ie, ionized).

[0170] The source gas then circulates in the gas circulation loop.

[0171] A filter device for filtering the circulating gas to remove impurities therefrom can advantageously be arranged in the gas circulation loop.

[0172] It may be advantageous to use means configured to create a vacuum in the compartment of the first enclosure in which the gas circulates and optionally for reintroducing the source gas into the circuit.

[0173] like Figure 5 As shown in detail, the assembly 100 comprises a laser 2. The light generated by the laser 2 is guided by a supply waveguide 20 to a reinsertion loop 3.

[0174] The supply waveguide 20 is, for example, a single-mode optical fibre. The supply waveguide 20 may also be a rectangular waveguide.

[0175] The reinsertion loop 3 comprises an input waveguide 21 configured to guide the light circulating in the reinsertion loop 3 to an optical input 32 of the housing 9 .

[0176] Preferably, the reinsertion loop 3 comprises a control portion comprising a waveguide 27 configured to collect a small portion, for example 0.1%, of the light circulating in the reinsertion loop and direct it to a photocell 28. This advantageously makes it possible to measure the light flux circulating in the reinsertion loop. Then, according to the measurement made by the photocell 28, the characteristics of the element with adjustable characteristics can be adjusted to keep the optical path length of the light reinserted into the loop 3 constant and to maintain the maximum light flux intensity.

[0177] Alternatively, the reinsertion loop 3 can also comprise an optical amplifier, for example by means of erbium-doped fibers, by means of the Raman effect or by means of semiconductor amplifiers.

[0178] The reinsertion loop 3 may include an adjustment electrode 29 connected to a generator, which may advantageously be arranged around a waveguide segment whose refractive index is adjustable according to an electric field, so as to adjust the refractive index of the segment and thus the optical length of the reinsertion loop. It is also advantageous that the power waveguide 20 has a segment with an adjustable refractive index, in particular in the case where the reinsertion loop 3 circulates light in wave packets rather than continuous light. The reinsertion loop 3 may also include a secondary adjustment electrode 30, which is configured to enable adjustment of the refractive index of a segment of the power waveguide 20 to allow the introduction of light from the laser 2 at a time appropriately selected according to the phase of the wave circulating in the waveguide 20.

[0179] The input waveguide 21 may be a single mode optical fiber and comprises an end portion 22 advantageously covered with an anti-reflection coating, which end portion is cleaved and polished in the form of a lens.

[0180] Preferably, a first set of focusing lenses 23 covered with an anti-reflection coating is arranged between the end 22 of the input waveguide and the optical input 32 of the housing 9 .

[0181] As an alternative to using an anti-reflection coating, the system can be configured so that light exiting the end 22 of the input waveguide is at the Brewster angle, thereby avoiding partial reflection of the light at the interface of the end 22 and the surrounding medium (atmosphere or partial vacuum).

[0182] Once the light enters the housing 9 via the optical input 32, a portion of the light generated by the laser interacts with the source material in the housing 9, thereby ionizing isotopes of the source material.

[0183] However, another portion of the light is able to pass through the housing 9 without interacting with the source isotope. In order to recover this non-absorbed light, the housing 9 may further comprise an optical output 33 configured to recover the non-absorbed light in the housing 9.

[0184] The light may optionally be reflected by one or more mirrors in the housing before reaching the optical output 33 .

[0185] Preferably, the second set of focusing lenses 25 is arranged between the optical output 33 and the end 26 of the output waveguide 34 to facilitate its reinsertion in the waveguide 34 .

[0186] The optical coupling between the optical output 33 and the end 26 may be performed in the same manner as the optical coupling between the optical input 32 and the end 22 .

[0187] The output waveguide 34 is optically connected to the input waveguide 21 to form a reinsertion loop 3 .

[0188] According to a specific embodiment, the input waveguide and the output waveguide may form only one single mode optical fiber.

[0189] Wave concentrating devices (such as mode blocking devices) can be integrated into the laser to superimpose different periods of a wave of coherent light, thereby reducing its duration while increasing its instantaneous power.

[0190] The duration of the output pulses from the wave focusing device advantageously corresponds to a pulse length of the order of the wavelength of the coherent waves generated by the laser; advantageously, the pulses are repeated with a frequency chosen so that a particle accelerated by a pulse reaches the target before a particle accelerated by a new pulse.

[0191] The wave concentrating device used is known per se. It can be of the coherent amplification network type, as described in the report “ICAN and 100GeV's Ascent”, J. Mourou et al., EuroNNAC, CERN conference, 3 May 2012.

[0192] Ionization systems using ionization methods other than by lasers can also be used in the context of the present invention, in particular by irradiation with X-rays.

[0193] The device according to the invention may also have one or more of the following features.

[0194] Cylindrical geometry

[0195] The second housing, the third housing and the wall for gamma-ray protection are preferably circularly symmetrical about the same axis. This symmetry makes it possible to use homogeneous material around the device, thereby saving its amount. The first housing advantageously has an elliptical shape so as to be able to withstand the pressure of the first target in gaseous form. The high pressure of the first target makes it possible in particular to reduce the size of the second housing. In one embodiment, for a hydrogen pressure of 15 atmospheres, the second housing may have a length of 30 cm to 1 m.

[0196] The first nuclear reaction

[0197] The source isotope in ion form is accelerated to a sufficient velocity using one or more strong electric fields so that upon impacting the first target, the kinetic energy accumulated by the ions is sufficient to allow nuclear fusion of the nuclei of the accelerated ions and the first target. The velocity of the ions may be, for example, 30 MeV to 100 MeV, preferably 40 to 80 MeV.

[0198] If the first isotope and the second isotope are both deuterium or deuterium and tritium, respectively, the source and target nuclei react to produce helium 3 and neutrons, or helium 4 and neutrons. The second isotope may also be a heavy isotope.

[0199] The first nuclear reaction (fusion or spallation) produces one or more neutrons.

[0200] The second nuclear reaction

[0201] Various elements or combinations of elements can be used as the second target for reacting with the neutrons emitted by the first nuclear reaction. In particular, compounds containing carbon, nitrogen and hydrogen can be used, but also helium, in particular helium 3 or argon mixed with gaseous protium, boron, boric acid, calcium, calcium hydride and magnesium and magnesium hydride. Preferably, the second target does not include actinides and has an atomic number less than or equal to 88, which are considered to be fissile and capable of causing a chain reaction of nuclear fission.

[0202] Calcium hydride advantageously has a high melting point (886°C) and does not decompose when heated, while releasing 8.4 MeV of energy by fusion of calcium with neutrons and incorporating two hydrogen atoms, which makes it possible to effectively contribute to slowing down neutrons. Helium 3, especially mixed with dihydrogen, is very advantageous even in gaseous form, helium 3 has a large effective cross section and releases 20.8 MeV of energy during fusion with neutrons. Boron is a solid and does not slow down neutrons, but it has a large effective cross section, making it very reactive with said neutrons, and it can therefore be inserted into other materials that slow down said neutrons, such as water, calcium hydride or dihydrogen.

[0203] The water is advantageously maintained under pressure so that it remains liquid. Alternatively, the water is in gaseous form, below or above its critical temperature of 374° C. In gaseous form, the moderator and the second target material are advantageously maintained under pressure, advantageously 15 to 100 atmospheres, for example 50 atmospheres, so that they can take up less space while absorbing and / or slowing down neutrons.

[0204] The probability of the presence of an actinide in a volume of material can be estimated by multiplying the number of atoms present in that volume by the probability of one of those atoms being struck by a neutron, raised to the power of δ, where δ is the difference between 89 and the atomic number of the second target element before being irradiated by the neutrons.

[0205] For example, if the volume of the second target is 5x10 -2 m 3 of zinc oxide, weighing 280 kg, and having 3443 moles of zinc and oxygen, it would take 1.7x10 22neutrons or 0.028 moles of neutrons to produce 1.5x10 10 J. The probability that a nucleus derived from 3443 moles of zinc will react with neutrons 58 times to become an actinide is 6.2x10 -296 , so the probability of the existence of actinide particles is 1.3x10 -268 .

[0206] Source and target elements

[0207] Various elements can be used as the second target.

[0208] In the reactions that may occur in the context of the present invention, a non-exhaustive list of examples of second targets is given in Table 2, together with their melting and boiling points, the energy released by the first fusion reaction of deuterium with tritium plus the energy of the second nuclear reaction with the second target and the neutron capture cross section.

[0209] [Table 2]

[0210] isotope Melting point(℃) Boiling point(℃) E(MeV) Cross section (barn) Argon 36 -189.4 -185.9 8.88 0.675 Argon 38 -189.4 -185.9 6.67 0.675 Boron 10 2300 2550 11.86 767 Carbon 12 3550 4827 15.07 0.0035 Calcium 40 839 1487 8.45 0.41 deuterium -259.1 -252.9 6.32 0.000519 Helium-3 -272.2 -268.9 20.79 5333 Hydrogen -259.1 -252.9 2.26 0.3326 Magnesium 25 648.8 1107 11.21 0.19 Magnesium 24 648.8 1107 7.41 0.05 Magnesium 26 648.8 1107 6.51 0.0382 Oxygen 16 -218.4 -182.9 4.19 0.0001 Sodium 23 97.8 883 7.03 0.53 Iron 56 1538 2861 7.72 2.59 Nickel 58 1455 2913 9.09 4.6 Nickel 60 1455 2913 790 29

[0211] "Stable isotope" means an isotope with a half-life greater than 10 12 Years of isotopes.

[0212] Other isotopes than those mentioned in Table 2 may also be suitable in the context of the present invention. The present invention may also allow the use of one or several different isotopes as a second target simultaneously.

[0213] The second target may be introduced into the third housing in gaseous, solid or liquid form.

[0214] Complex targets and speed reducers

[0215] The invention allows the use of materials consisting of complex molecules, i.e. molecules consisting of several different elements and mixtures of molecules, as materials for slowing down neutrons and / or as a second target. The use of complex molecules makes it possible in particular to manipulate target elements in a preferred state (e.g. gaseous, liquid or solid) when these separated elements are in different states under the implementation conditions of the invention. This can in particular make it possible to facilitate the removal of the heat generated when the elements in the complex molecules form a fluid and the separated elements form a solid. The use of complex molecules also makes it possible to utilize the heat generated by the second nuclear reaction in the second target to facilitate one or more chemical reactions there.

[0216] Thus, the third housing containing the second target may advantageously contain one or more catalysts to utilize the heat generated in the second target to promote a chemical reaction.

[0217] A chemical reaction could be, for example, the decomposition of methane:

[0218] CH4→C+2H2, at this time methane is heated to a temperature above 1200℃.

[0219] The chemical reaction can also be the reduction of zinc oxide:

[0220] ZnO+H2→Zn+H2O, this endothermic reaction can occur at 1000℃.

[0221] ZnO+CO→Zn+CO2, at 1000℃.

[0222] ZnO→Zn+ 1 / 2O2, at 1727℃.

[0223] Chemical reactions can also be used to synthesize ammonia via the Haber process:

[0224] Over a bed of iron catalyst at 350°C.

[0225] Gamma ray protection

[0226] The energies involved in nuclear reactions are very large and the device according to the invention may generate considerable gamma radiation.

[0227] In an advantageous variant, protection against gamma radiation can therefore be arranged around the device.

[0228] The thickness of this protection against gamma rays can be determined according to the power of the gamma radiation generated, which depends on several parameters related to: the arrangement of the device, its dimensions, the energy production of the average nuclear reaction during the use of the device, and also the tolerance to the power of gamma radiation reaching the external environment.

[0229] According to the inventors' calculations, for the first deuterium-deuterium nuclear reaction and the second neutron-helium 3 nuclear reaction, an 18 cm thick tungsten wall or a 28 cm thick lead wall 40 cm away from the center of the device where the gamma rays are generated keeps the annual gamma radiation dose below 5 mSv, and in the case where the vehicle engine is more than 1 m away from the passengers, 6.5x10 9 joules, of which 86% are produced by gamma rays and 14% by slowed neutrons, the acceptable radiation dose is fairly divided between neutrons and gamma rays, or 3.9x10 11 In the case of a Joule power station, which includes the device according to the invention, its employees maintain a distance greater than 50m from the device. For example, this distance can be further shortened by adding a concrete wall between the place where employees frequently go and the device.

[0230] Protection against radiation passing through the supply openings

[0231] Gamma rays follow a straight line trajectory from their emission location. Therefore, preferably, the orifice opening on the exterior of the device should not be aligned with the location of the nuclear reaction, or should not include an aligned perspective relationship, whether between the source ions and the first target or between the neutrons and another material of the device including the second target. The orifice may, for example, have a spiral form and be arranged within the material that absorbs the gamma rays. Alternatively, the opening on the exterior of the device may include two orifices: a first orifice arranged to pass through a first material or volume, the shielding gamma rays of the first material or volume being aligned with the location where the gamma rays are generated, a second material or volume that absorbs the gamma rays being arranged on the axis of the alignment, and a second orifice being arranged between the two volumes away from the axis of the alignment.

[0232] Protects against neutrons and absorbs said neutrons

[0233] Neutrons from the first nuclear reaction in the second enclosure must first be slowed down and then absorbed by the second target material to fuse with the latter. To prevent the slowed down neutrons from leaving the device, a material that reacts easily with the neutrons (e.g., boron 10 or helium 3) is arranged around the device, or around one or more materials that slow down the neutrons.

[0234] Neutron absorbing materials

[0235] Helium may advantageously be placed under supercritical temperature and pressure conditions, for example at a pressure greater than 2.26 atmospheres, making it a quasi-fluid and allowing it to have a density greater than its gaseous density. Boron may be combined with other elements to form other chemical species, in particular boron sesquioxide (B2O3), which has a melting point and boiling point of 450°C and 1860°C, respectively, so as to be able to be handled in liquid form and thus replaced when consumed by the nuclear reaction on the one hand, and used as a heat transfer fluid on the other hand. Since the nuclear reaction produces a release of gamma-ray energy, gamma-ray shielding consisting of a material that absorbs gamma-ray energy is preferably arranged around the equipment in which the second nuclear reaction may occur.

[0236] Materials used to slow down neutrons

[0237] The material used to slow down the neutrons can be water, preferably a liquid under supercritical conditions at a temperature below the critical temperature of 374.15°C or at a pressure above its critical pressure (220 atm). Alternatively, other materials in solid or liquid form, in particular protium-rich materials, such as calcium hydride CaH2 or CaD2, calcium hydroxide (Ca(OH)2), aluminum hydroxide (Al(OH)3), nickel (II) hydroxide (Ni(OH)2), or alcohols, polymers, alkanes such as methane CH4, preferably maintained at a pressure greater than the critical pressure of the alkane (which is 46 atmospheres), or dihydrogen H2 maintained at a pressure above its critical pressure (13 atmospheres), helium 3 or helium 4, argon 36, methane, or water in liquid or solid form, dihydrogen borate H2BO3, polystyrene, sodium hydroxide NaOH with a boiling point of 1388°C and chemical stability, potassium hydroxide KOH with a boiling point of 1327°C and chemical stability, decaborane B 10 H 14 .

[0238] Therefore, according to the inventors' calculations, a 3 mm thick layer of supercritical helium 3, boron 10 or boron sesquioxide can allow more than 99% of slow neutrons to be absorbed, while a 10 cm thick wall of water or a 6 cm thick calcium hydride or a 25 cm thick layer of dihydrogen can absorb more than 99% of slow neutrons under supercritical conditions. 3 The density of neutrons can reduce the fast neutron flux by 99%. Neutron fusion reactions with helium-3 are particularly energy-producing, releasing about 20 MeV of energy per isotope; neutron fusion reactions with boron-10 release about 11 MeV of energy per isotope.

[0239] For example, according to the inventors' calculations, the use of a 26 cm thick layer of CaH2 surrounded by a 0.62 cm thick layer of B2O3 can reduce the neutron dose leaving the device by a factor of 9x10 8 One-tenth; this factor corresponds to the acceptable dose for gamma ray protection of the above-mentioned vehicle engines.

[0240] Mixture of target material and moderator

[0241] A second target material may also be arranged in the moderator, thereby limiting the flux of slow neutrons directed to the outside of the device and thus limiting the nuclear reactions occurring around the moderator. A tube for circulating the target material may be installed in particular in the moderator. Alternatively or in combination, the material for moderation may also be used as target material, which target material may be, for example, water in liquid form or boric acid H2BO3 or metaboric acid H3B3O6 maintained at their respective decomposition temperatures (185°C and 300°C).

[0242] Protection against neutrons passing through the supply port

[0243] In such Figure 3 In the embodiment shown, the third housing may include apertures 147. These apertures may allow the passage of neutron flux to the exterior of the device.

[0244] The orifice 147 allows the introduction of material (e.g. liquid, gas, ions, electric current) into the space of the device where neutrons circulate, such as the first enclosure, the second enclosure or the third enclosure. The orifice 147 preferably has a solenoid shape within the material that slows down the neutrons, which itself is preferably covered by a neutron absorbing material at its interface with the orifice.

[0245] If the orifice allows the introduction of accelerated ions, the neutrons entering the orifice will encounter only very few molecules or ions and will be deflected very little there, but will not be able to leave in a straight line. A winding comprising an electrical conductor around the solenoid, within the ion moderator and / or outside the latter may allow a magnetic field to be formed within the orifice parallel to the axis of the solenoid, thus retaining the ions in the solenoid orifice.

[0246] The thickness of the material slowing down the neutrons around the cavity protecting them from escape is preferably greater around the solenoid orifice so that neutrons that have traveled inside the orifice may be slowed down by at least as much material as if they had not traveled through.

[0247] In a second variant, the ion velocity at the tube outlet (slowed down by the Bragg effect in gaseous deuterium) is arranged so that the edges and ends of the deuterium ion beam are either very close to the space, or very close to the confining walls of the space (in which the second nuclear reaction occurs), for example 2 mm, to reduce the space in which the released neutrons can react with deuterium.

[0248] Separation of various isotopes

[0249] Most often, the element produced by the second nuclear reaction is a different isotope of the same element. According to an advantageous embodiment, the device therefore has means for separating the isotopes produced from the second target isotope, in particular if the second target isotope is less reactive with neutrons or if they produce different amounts of energy.

[0250] The separation can be carried out in particular by phase differentiation at a temperature of 0.8 K, by membrane filtration or by selective ionization by a laser or by a Stern-Gerlach apparatus.

[0251] According to one embodiment, the mixture can be enriched with helium 3 by cooling at 0.8 K by the method described in the article "Helium 3 isotope separation and lambda front observation", Kempiński et al., Separation and Purification Technology, Volume 210, February 8, 2019, Pages 276-280.

[0252] According to an alternative embodiment, helium 3 can be separated from helium 4 by filtering at 30K using a membrane as described in the article “Isotopic separation of helium through graphyne membranes: a ring polymer molecular dynamics study”, Bhomwick et al., Physical Chemistry Chemical Physics, Issue 34, 2021, in particular a graphyne membrane.

[0253] According to another embodiment, the separation of isotopes can be accomplished by means of a laser with circularly polarized light and an electric field, by which only elements having a magnetic moment are ionized and then moved by the electric field, as described in the article “Use of angular-momentum selection rules for laser isotope separation”, Balling et al., Appl. Phys. Lett. 29, 411, 1976, or by centrifugation.

[0254] Alternatively, a jet of a liquid or gaseous mixture of helium 3 / helium 4 can be subjected to an inhomogeneous magnetic field, as described by Stern and Gerlach ("Der experimentelle Nachweis der Richtungsquantelung imMagnetfeld", Gerlach W., Stern O., Zeitschrift für Physik 9(1):349-352, 1922), the isotopes of helium 4 having a nuclear spin of 0 and helium 3 having a nuclear spin of 1 / 2, helium 4 will not be deflected by the magnetic field, but helium 3 may be.

[0255] Several sequential isotope separation cycles may be performed before reinserting the second target into its housing, especially if fusion reactions between neutrons and isotopes produced by the second nuclear reaction are undesirable because they may produce unstable elements or may have a reactivity or release energy with neutrons that is significantly different from the reactivity and energy release of nuclear fusion reactions of neutrons with one or more other second target isotopes.

[0256] Regeneration of neutron absorbing materials

[0257] The neutron absorbing material is advantageously replaceable, in particular the part thereof that most absorbs neutrons. This replacement may be mechanical, the device being configured to allow such replacement, or it may be performed by replacing the fluid, whether the latter is in liquid, gaseous or supercritical form. Furthermore, means for separating the material produced by the nuclear reaction of the second target material may be arranged in the device.

[0258] Separation of the products of the second target material can be accomplished, for example, by phase differentiation, when the second target absorbs neutrons to produce an unstable element that decays into a different element, the two elements having different melting, boiling or sublimation temperatures. This is particularly the case when tritium decays into helium 3, boron 12 decays into carbon 12, carbon 15 decays into nitrogen 15, nitrogen 16 decays into oxygen 16, oxygen 19 decays into fluorine 19, and sodium 24 decays into magnesium 24. In the case of helium 5, it decays into helium 4 by releasing a neutron, which is the opposite of the fusion reaction that could produce it. In addition, it has a lifetime of 7x10 -21 s, which means that it barely reacts with the neutrons from the first nuclear reaction. When helium-3 absorbs neutrons, it thus gradually transforms into helium-4.

[0259] Cooling lines and plates

[0260] The walls for shielding against gamma rays and the optional second and third housings may also be configured such that a cooling fluid circulates within them, for example in channels arranged in the walls or between a plurality of consecutive walls.

[0261] The cycle of gaseous deuterium

[0262] When the first and second isotopes are deuterium, it is worth noting that the first nuclear reaction fusing the two deuterium nuclei is very exothermic, but the energy produced is essentially present in the kinetic energy of the produced neutrons and helium. The Bragg effect slows down the ions in the second shell filled with gaseous deuterium and also heats the gas, which can advantageously circulate in a cooling loop leaving the device. The recovered heat is advantageously used, for example for power generation.

[0263] Ion beam

[0264] Ions of the first isotope (e.g. deuterium ions) are introduced into the second housing via a supply channel, at the end of which a membrane is preferably arranged, the membrane being configured to prevent gaseous deuterium from entering the channel, such as Figure 1 This therefore allows a vacuum to be maintained in the channel, thereby facilitating the transport of ions.

[0265] The membrane consists of, for example, six layers of graphene, graphane or hexagonal boron nitride. The ions at the outlet of the duct are preferably kept concentrated by means of a longitudinal magnetic field in the same direction as the axis of rotation of the second housing, generated by a solenoid surrounding the second housing. The supply channel for the ions is preferably covered internally with a dielectric film to prevent electrons from being stripped from the inner wall of the channel.

[0266] Ionization system

[0267] According to one embodiment, the ionization system comprises:

[0268] - Lasers,

[0269] - an input waveguide configured to direct light emitted by the laser towards an optical input to the housing, the optical input being configured to allow illumination of a source material by the emitted light.

[0270] The laser may be configured to emit light whose instantaneous power is sufficient to allow ionization of the source material. The ionization system may also include a wave concentrator configured to superimpose multiple cycles of the light emitted by the laser so as to increase the instantaneous power of the emitted light, the wave concentrator preferably being of the coherent amplification network type. Furthermore, the device may advantageously include an output waveguide configured to guide light not absorbed by the source material from the optical output of the housing to the optical input of the housing, and the housing may include a plurality of mirrors configured to reflect the light emitted by the laser between the optical input and the optical output so as to illuminate the source material multiple times.

[0271] Alternatively, ionization can be obtained, for example, by irradiating the first isotope with X-rays, for example generated by an X-ray tube placed in the first enclosure, the wavelength of the X-rays emitted by the tube being less than Planck's constant multiplied by the speed of light in a vacuum and divided by the ionization energy of the first isotope. The walls of the first enclosure (except for the apertures required for the passage of ions and the entry of the first isotope) are preferably covered or flanked by X-ray mirrors, as described in the article "SOFT X-RAY REFLECTIVITY: FROM QUASI-PERFECT MIRRORS TO ACCELERATOR WALLS", F. R. Cimino, DOI: 10.5170 / CERN-2013-002.105, arXiv: 1308.1295, or using Bragg mirrors produced, for example, by atomic layer deposition techniques.

[0272] Lasers for ionization systems

[0273] exist Figure 4 The embodiment shown and Figure 5 In the embodiment shown, the source isotope is ionized by a laser.

[0274] The wavelength of the light generated by the laser is, for example, 369 nm, 269 nm or 182 nm. The generated wavelength may also be smaller, and lasers with wavelengths as small as 13.5 nm are known.

[0275] The light can be generated by a laser diode. Continuous wave lasers such as VECSELs can also be used.

[0276] The wavelength of 369 nm can be obtained, for example, by mixing laser light of 1470 nm with the second harmonic of laser light of 985 nm.

[0277] The wavelength of 269 nm can be obtained using the third harmonic of laser light having a wavelength of 808 nm.

[0278] The wavelength of 182nm can be obtained by mixing the fifth harmonic of the 1064nm laser light with the 1260nm laser light. The mechanism for obtaining harmonic and wavelength mixing is described in the application WO 2018 / 128963 Al, for example.

[0279] The laser beam may be magnified or focused by an optical lens so that the power per unit area of ​​the laser beam does not exceed the dislocation limit of certain materials used in the ionization device.

[0280] The dimensions of the lens are advantageously chosen to allow the laser beam to be focused over a sufficient length in the first housing, where ionization of the source occurs, and then to reach the lens of the reinsertion loop.

[0281] The frequency of the light generated by the laser can be doubled or quadrupled by passing through properly selected nonlinear and asymmetric crystals. The frequency can also be multiplied by five using a harmonic generation method, according to which the laser beam is passed through a rare gas, such as argon.

[0282] It is also possible to use 361 nm coherent light produced by a gallium nitride (GaN) laser diode, with a bandgap of 3.44 eV; or 188 nm coherent light produced by an indium gallium nitrite (InGaN) laser, where the proportion of gallium is chosen to produce a semiconductor material with a bandgap of 3.3 eV, whose frequency is doubled by passing through a crystal (e.g., a borate fluoride crystal), such as KBe2BO3F2 (KBBF), which is transparent to wavelengths as small as 147 nm and supports up to 9.1011 W / cm 2 of power.

[0283] It is also possible to use 166 nm coherent light generated by quantum well lasers.

[0284] The wave train produced by the laser combined with mode suppression repeats at a frequency that can be from 0.1kHz to 10kHz. However, as described above and Figure 2 The first reinsertion loop shown for a discontinuous wave train has the effect of causing the wave to circulate in the loop, thereby repeating the wave train with a frequency equal to the speed of light in the loop divided by the total length of the loop.

[0285] The light circulating in the reinsertion loop of the discontinuous wave train is subject to power losses caused by attenuation between two consecutive pulses due to a certain degree of opacity of the material guiding the light and its passage through the ionization chamber.

[0286] The reinsertion loop can only reinsert light with wavelengths greater than 150 nm, since few glasses or crystals are transparent to smaller wavelengths.

[0287] It is not necessary to use a wavelength of ionizing light whose photon energy is greater than the ionization energy of the gas, as disclosed in the article “Laser stripping of hydrogen atoms by direct ionization”, Brunetti et al., New Journal of Physics, Vol. 17, May 2015.

[0288] Acceleration of ions

[0289] Ionization systems produce ions that are accelerated by electric fields, either in linear accelerators that can accelerate a continuous flux of ions at a continuous voltage, or in cyclotrons or synchrotrons that can accelerate ion packets between two electrodes that alternate between a positive and negative potential difference.

[0290] Linear Accelerator

[0291] Thus, the ion accelerator may be linear, comprising a high voltage generator electrically connected to a first electrode arranged in the housing, preferably at a first end of the housing, and electrically connected to a second electrode, such as in combination with Figure 5 As described.

[0292] Accelerating Cyclotron

[0293] Alternatively, the accelerator comprises a cyclotron and the ions are generated or sent as packets in the cyclotron, preferably near the centre thereof.

[0294] Accelerating synchrotron

[0295] As another alternative, the accelerator comprises a synchrotron, and the ions are produced or sent as packets in the synchrotron, the magnetic field limiting the ion trajectories being variable and allowing the ions to be confined in two half-pipes rather than the dees of a cyclotron.

[0296] Inner walls of cyclotrons, synchrotrons and maintenance electrodes

[0297] The inner walls of the cyclotron or synchrotron and the walls of the maintenance electrodes described below are advantageously covered with a dielectric layer, for example of a polymer or glass, which resists the electric field generated by the potential difference applied to the two dees of a cyclotron, the two tubes of a synchrotron or the various maintenance electrodes.

[0298] Hybrid Accelerator

[0299] Alternatively, the ions are accelerated by a combination of a linear accelerator and a cyclotron and / or a synchrotron, the ions emitted in packets from the linear accelerator being injected into a cyclotron near its center, for example, to be directed to the exit of a second linear accelerator. If the ions are injected into the cyclotron with a velocity having a component along the axis of the cyclotron that is not zero, the ions are preferably slowed in this direction by an electric field of the same direction and opposite induction generated by electrodes positioned near or around the center of the cyclotron, advantageously allowing this component of the velocity to be cancelled while the ions still circulate in this region.

[0300] The various accelerators used are preferably electrically isolated from one another, their power supplies (for example if they are alternating current) being isolated from one another by transformers having windings.

[0301] The ion accelerator or accelerators are preferably gas-free in order to avoid the Bragg effect of ion braking and are therefore preferably protected at their inlet and outlet by membranes permeable to the ions and impermeable to the gas present outside, and are equipped with pumps that create a vacuum there. The device is then preferably arranged so that the membranes can be replaced intermittently or continuously, the latter being able to decay during nuclear reactions with the accelerated ions or by simple heating due to the passage of ions.

[0302] Maintenance electrode

[0303] When the ions enter the first target (eg gaseous deuterium), the ions slow down. Therefore, it can be ensured that there is an electric field in the first target which prevents the ions from slowing down.

[0304] Advantageously, if Figure 1 As shown, one or more maintenance electrodes are arranged at the end of or within the second housing containing the first target, the electrodes being configured to generate an electric field and maintain a constant velocity of the ions despite effects that cause ion slowing, in particular the Bragg effect.

[0305] Maintaining the Cyclotron

[0306] Alternatively, if the ions are grouped in packets, the cyclotron may be used to maintain their speed or reaccelerate them as they pass from one dee to another. Ions of the first isotope may then enter the cyclotron, preferably having been accelerated by an accelerating cyclotron or linear accelerator external to the cyclotron; the second isotope (e.g. deuterium or gaseous tritium) ensuring its slowing down until the first pass between the two dees (if the latter are wholly or partly outside the region between the two dees, e.g. inside one or each dee).

[0307] A channel for supplying ions from the first isotope to the second enclosure

[0308] The channel for supplying ions in the second enclosure is preferably free of gas to avoid that the ions are braked there. Advantageously, its inner wall is coated with a dielectric layer to prevent electrons from being stripped from it. It can be arranged to pass inside one or more solenoids that generate a magnetic field, so that the ion beam can be prevented from diverging. The ion beam can be directed by magnetic lenses and magnetic fields, allowing it to have a spiral trajectory, or change direction, in particular before it enters the second enclosure containing the first target.

[0309] The device according to the invention can be used in the following applications.

[0310] Using zinc oxide for gamma protection

[0311] exist Figure 3 In the preferred embodiment shown, zinc oxide is used both for gamma radiation protection and for conversion into zinc and oxygen.

[0312] Zinc oxide is a powder that decomposes into zinc and oxygen at about 1727°C. The powder can be introduced as a material for neutron and gamma ray protection. The gamma radiation generated by the device heats the powder, which decomposes into zinc and oxygen, both of which can be discharged in a gaseous state, preferably at a temperature above 1727°C. The zinc and oxygen can be separated from each other, for example by centrifugation, and then cooled, or very quickly cooled without first being separated. Rapid cooling causes the zinc to condense into a liquid or solid before it recombines with the oxygen.

[0313] Orifices are advantageously provided to allow the supply of zinc oxide and the exhaust of gases. It is also possible to incorporate means for circulating and compacting the zinc oxide powder ( Figure 5 ) and pipes, for example made of tungsten, allow a cooling fluid to circulate in the zinc oxide powder. The cooling fluid is, for example, tin, which has a melting point and boiling point of 232°C and 2270°C and an atomic number of 50, which is advantageously much lower than 88.

[0314] The regenerated zinc and zinc oxide can be used, for example, in a liquid fuel cell SOFC (acronym for “solid oxide fuel cell”) as described below, to generate electrical energy.

[0315] The first target, for example gaseous deuterium, in the second housing is advantageously cooled by forced convection in a cooler, thereby allowing recovery and utilization of heat generated, in particular, by the Bragg effect in the second housing.

[0316] Using lithium-6 as a secondary target for tritium production

[0317] Tritium can be obtained by the exothermic decomposition of lithium-6 activated by neutrons according to the following reaction:

[0318] 6 Li+n→ 4 He+T+4.8MeV

[0319] in 6 Li is lithium 6, 4 He is helium 4, T is tritium and n is neutron, the kinetic energy of helium is 2.05 MeV and the kinetic energy of tritium is 2.75 MeV, totaling 4.8 MeV.

[0320] Therefore, in a preferred embodiment, lithium 6 is used as the second target for absorbing neutrons.

[0321] Lithium 6 is preferably stored at a temperature above 600°C. Advantageously, about 30 ppm of carbon is mixed with the lithium to act as a catalyst for the LiT production reaction, equivalent to lithium hydride in which hydrogen is replaced by tritium. Tritium can then be separated from lithium by adding sulfur dioxide at above 50°C to form tritium T2 and lithium dithionite Li2S2O4.

[0322] Lithium dithionite can be regenerated into lithium and sulfur dioxide by electrolysis in carbonate-based electrolytes, as described in detail in the following article: High-efficiency and high-power rechargeable lithium–sulfur dioxide batteries exploiting conventional carbonate-based electrolytes, Park, H., Lim, HD., Lim, HK. et al. Nat Commun 8, 14989 (2017). Https: / / doi.org / 10.1038 / ncomms14989.

[0323] The compound LiT, which can be isolated, for example, by decantation, is denser than lithium.

[0324] Preferably, means for exhausting helium generated in the third enclosure containing lithium is also provided.

[0325] Alternatively, the lithium 6 remains liquid at a temperature above 180° C. but below 600° C. Tritium does not react with gaseous lithium evaporating from the liquid lithium in the gas bubble, nor does it react with helium. Advantageously, the LiT residue is extracted from the lithium, for example by decantation, and then the tritium is separated from the lithium by adding sulfur dioxide as described above.

[0326] Hydrogen production via the sulfur-iodine cycle

[0327] Advantageously, the heat released by the first and second nuclear reactions can be recovered in various heat exchangers or by circulation of gases, liquids or solids in the second and third housings of the device according to the invention.

[0328] The chemical reactor can be particularly useful for producing hydrogen by pyrolysis using a sulfur-iodine cycle, as described in the document “Sulfur-Iodine Thermochemical Cycle”, P. Pickard, Sandia National Labs, May 17, 2006.

[0329] An oxide-cerium cycle may also be used.

[0330] The heat generated by the fusion reaction can be used to provide heat for the various endothermic reactions of the sulfur-iodine cycle.

[0331] Water Heating

[0332] The method can also be used to heat water in liquid or gaseous form, use the water as a material to absorb the generated gamma radiation, or use it as a moderator liquid or liquid coolant.

[0333] Production of olefins

[0334] The heat generated in the device according to the invention can be advantageously used to heat alkanes in the presence of a catalyst (e.g. platinum, palladium, rhodium, ruthenium, iridium, osmium or chromium) in solid or liquid form as a second target or for gamma ray shielding, or in liquid or gaseous form as a liquid coolant, or for absorbing gamma rays. Alkanes heated in the presence of a catalyst produce olefins, e.g. butane is converted into butenes.

[0335] CO2 reduction

[0336] For example, CO2 can be converted to CO at 750°C in a high temperature electrolyzer whose electrolyte is O 2-Ionic conductor. The electrolyte can be formed, for example, by a 150 μm thick 10Sc1CeSZ layer (ZrO2 doped with 10% of the molecules as Sc2O3 molecules and 1% of the molecules as CeO2 molecules).

[0337] Reduction of methane

[0338] Methane can advantageously be heated by the heat generated by the device according to the invention. Methane can be decomposed according to the following reaction:

[0339] CH4→C+2H2, at this time methane is heated to a temperature above 1200℃.

[0340] Advantageously, the produced carbon can be deposited on diamond to increase the size of the latter.

[0341] Cement Manufacturing

[0342] A fluid, such as gaseous nitrogen, can be used as a cooling fluid produced by the apparatus according to the invention to be heated to a temperature of about 1500° C. The clay and limestone can be heated a second time by a heated nitrogen stream. Alternatively, the mixture of clay and limestone can be heated by absorbing gamma radiation generated by the apparatus according to the invention.

[0343] Cement can advantageously be made from heated clay and limestone.

[0344] The second and third shells and the shell containing the material for shielding against gamma radiation are preferably made of a material having a liquefaction temperature higher than 3400° C. (eg, tungsten or carbon).

[0345] Iron Manufacturing

[0346] The device according to the invention can be used to heat, for example, iron oxide as a material absorbing gamma rays.

[0347] At 2000°C, ferric oxide can be reduced by carbon monoxide to produce carbon dioxide according to the following reaction:

[0348] Fe2O3+3CO→2Fe+3CO2.

[0349] Alternatively, dihydrogen, for example produced by the above-mentioned iodine-sulfur process, can also be mixed with carbon monoxide so that the reduction of ferric oxide occurs according to the following reaction: Fe2O3+CO+2H2→2Fe+CO2+2H2O.

[0350] Therefore, iron is obtained starting from ferric oxide.

[0351] Power Generation

[0352] The energy generated by the device according to the invention may allow electricity to be generated, in particular by combining the device with an electrical generator by redox.

[0353] For example, electricity can be generated by a zinc battery or by producing hydrogen which is then consumed in a hydrogen battery.

[0354] Good conversion rates of heat to electricity may allow sufficient electricity to be generated for accelerating ions of the first isotope and for providing consumable electrical energy.

[0355] Generating electricity through zinc batteries

[0356] According to an advantageous variant, electricity can be produced by regenerating zinc oxide to zinc and then using the zinc as an electrode in a zinc-air battery. The energy efficiency is limited on the one hand by the efficiency of the zinc-air battery, which is about 84% when operating at 1.4 V at a theoretical voltage of 1.65 V, and on the other hand by the efficiency of the zinc regeneration. The latter is reduced to 100% by carbon or carbon monoxide, to 100% by calcining zinc oxide at 1727° C. to zinc and oxygen, or to 85% by hydrogenation of zinc oxide if hydrogen is produced by a sulfur-iodine cycle.

[0357] If the second target includes helium 3, the reaction of neutrons with helium 3 can produce an average of 20.79 MeV per neutron. According to the inventors' calculations, the first nuclear reaction that produces neutrons can produce 3.3 MeV (for deuterium as the first and second isotopes); the acceleration of ions requires 55 MeV to produce neutrons for 76% of the ions.

[0358] The nuclear energy generation level is then ((20.79+3.3)*0.76+55) / 55=132%. If only 84% of the released and recovered energy is converted into electrical energy, then 132% x 84% = 111% of the electrical energy used for ion acceleration is recovered from the device, so the net power generation is 11% of the energy required for ion acceleration.

[0359] The generation of useful levels of energy beyond that necessary for ion acceleration can be increased by using other methods of converting thermal energy into electrical energy, such as generating electricity through hydrogen cells, in which hydrogen is produced by a sulfur-iodine cycle; generating electricity through zinc-air cells; through hydrogenation of zinc oxide or reduction of zinc oxide by carbon and carbon monoxide; or through the use of liquid zinc SOFC cells.

[0360] Generate electricity through hydrogen cells

[0361] It is also possible to generate electricity by producing hydrogen (for example by the iodine-sulfur cycle) which is then used in fuel cells. The efficiency of these fuel cells is close to 60%. Advantageously, the fuel cells used may be SOFC type cells from which the heat released can be recovered to co-supply the device for producing hydrogen, giving an electricity / heat yield of 77%, or even 79.5% if a cycle for converting low heat with an efficiency of 10% or more is used (for example the Rankine cycle).

[0362] Utilizing the sulfur-iodine cycle

[0363] The sulfur-iodine cycle allows the production of hydrogen with a large amount of heat while rejecting a small amount of heat at 120°C, with the inventors estimating the heat energy loss to be about 15%. The reaction I2+SO2+2H2O→2HI+H2SO4 releases 15% of the heat required for the two endothermic reactions: 2H2SO4→2SO2+2H2O+O2 and 2HI→I2+H2.

[0364] The heat from the exothermic reaction of the sulfur-iodine cycle can be advantageously used in the organic Rankine cycle, making it possible to convert 10% of this energy into electrical energy, thereby increasing the energy conversion efficiency to about 79%.

[0365] Using zinc oxide hydrogenation

[0366] The heat generated by the device according to the invention can be used to regenerate zinc starting from dihydrogen and zinc oxide produced by the Daniel cell, wherein part of the electricity generated can be used to accelerate the deuterium ions. The chemical reaction is:

[0367] ZnO+H2→Zn+H2O.

[0368] This endothermic reaction can occur in a mixture of 87% dinitrogen and 13% hydrogen at 1000°C, but advantageously without dinitrogen and preferably in the absence of water, as described in the following article: Lew, S., Sarofim, AF, & Flytzani-Stephanopoulos, M. (1992). The reduction of zinc titanate and zincoxide solids. Chemical Engineering Science, 47(6), 1421-1431.

[0369] Zinc oxide can be heated by the gamma radiation produced by the apparatus according to the invention, extracting zinc and water in gaseous form.

[0370] Reduction of zinc oxide by carbon and carbon monoxide

[0371] Alternatively, the zinc can be regenerated by reduction with carbon at temperatures between 1200° C. and 1400° C. or with carbon monoxide at temperatures between 900° C. and 1000° C. Both reactions are endothermic and produce zinc and carbon dioxide which is regenerated to carbon and oxygen, for example by high temperature electrolysis.

[0372] SOFC cells with liquid zinc

[0373] Liquid zinc SOFC cells may be used, in which zinc, particularly zinc regenerated from zinc oxide, is raised to a sufficiently high temperature to be in a liquid state.Solid electrolytes may be used, such as lanthanum strontium cobalt ferrite separated from zinc by a cerium oxide layer.

[0374] Zinc then constitutes the anode. Oxygen is supplied to a cathode consisting of, for example, strontium lanthanum manganite, where it is ionized. The ionized oxygen rejoins the anode by passing through a solid electrolyte.

[0375] The use of liquid zinc SOFC cells can improve the reduction efficiency of zinc oxidation-reduction relative to conventional cells on the one hand, and on the other hand, can utilize the reaction of zinc oxide regeneration to zinc and circulate the hot oxygen released in the reaction. The operating temperature is preferably higher than 420°C (i.e., the melting point of zinc) and lower than 902°C (i.e., its vaporization temperature). Preferably, the operating temperature is 600°C.

[0376] The present invention is not limited to the above-mentioned embodiments. Specifically, the devices and methods mentioned or shown can be combined in different ways to form other variations not shown.

Claims

1. An apparatus for conducting a nuclear reaction, comprising: - a source material comprising a first isotope, arranged in a first enclosure, - an ionization system configured to at least partially ionize the source material, - an ion accelerator configured to accelerate ions originating from the source material to a first target arranged in a second enclosure and containing a second isotope, so as to allow a first nuclear reaction between the first isotope and the second isotope, - a second target, arranged in the second enclosure or in a third enclosure separate from the second enclosure, to allow neutrons produced by the first nuclear reaction to react with nuclei of atoms of the second target, the first isotope is a hydrogen isotope and the second isotope is a hydrogen isotope or a heavy isotope, If the second isotope is a heavy isotope, the first nuclear reaction is a spallation reaction, and if the second isotope is a hydrogen isotope, the first nuclear reaction is a fusion reaction.

2. The apparatus according to claim 1, wherein the ionization system comprises: - Lasers, - an input waveguide configured to direct light emitted by the laser towards an optical input of the first housing, the optical input being configured to allow the emitted light to illuminate the source material.

3. The apparatus of claim 1, the ionization system comprising an X-ray emission system disposed in the first housing to at least partially ionize the source material.

4. The apparatus according to any one of claims 1 to 3, the ion accelerator comprising a high voltage generator electrically connected to a first electrode and a second electrode, the first electrode and the second electrode being arranged in the second housing, The generator and the first and second electrodes are configured to generate an electric field for accelerating ions from the source material to the first target to induce fusion of nuclei of ions from the source material with nuclei of the first target.

5. The device according to any one of claims 1 to 4, at least the first housing and / or the second housing being surrounded by a wall comprising a material absorbing gamma rays, such as tungsten or lead.

6. The device according to any one of claims 1 to 5, the second target being arranged in the third housing, the third housing being arranged around the second housing.

7. The device according to any one of claims 1 to 6, comprising a cooling circuit, the cooling fluid of which circulates at least partially in the wall of the second housing and / or in the wall of the third housing.

8. The apparatus of any one of claims 1 to 7, the first isotope and the second isotope being selected from deuterium and tritium, only one of which is tritium.

9. The apparatus of any one of claims 1 to 8, the first isotope being deuterium in gaseous form, the deuterium circulating in a loop comprising the first enclosure, the loop being configured to cool the deuterium.

10. The device according to any one of claims 1 to 9, the second target comprising lithium 6, preferably consisting of lithium 6.

11. Use of the device according to any one of claims 1 to 10 as a chemical reactor for heating chemical products, allowing chemical reactions, in particular endothermic chemical reactions, with or without catalysts, wherein the chemical products preferably circulate in the walls of the second and / or third housing to ensure their cooling and / or circulate in the second and / or third housing.

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