Method for producing he-3, nuclear reaction generating apparatus, and nuclear reaction generating method
The nuclear reaction generating device and method efficiently produce He-3 by controlling temperature and pressure in a sealed container with a CNZ alloy, addressing the challenges of radioactive byproducts and plasma control in existing He-3 production and fusion energy technologies, enabling safe and sustainable energy generation.
Patent Information
- Application Number
- PCT/JP2025/025517
- Authority / Receiving Office
- WO · WO
- Patent Type
- Applications
- Current Assignee / Owner
- Priority Date
- 2025-01-27
- Filing Date
- 2025-07-16
- Publication Date
- 2026-02-05
AI Technical Summary
Current methods for producing helium-3 (He-3) involve the generation of radioactive materials, such as tritium, and require complex nuclear reactors or accelerators, posing risks and limitations on industrial facilities, while nuclear fusion energy faces challenges in plasma control and the difficulty of achieving practical application due to issues like turbulence in plasma states.
A nuclear reaction generating device and method that utilizes a heating element to induce interactions between hydrogen atoms within a sealed container, controlling the temperature and pressure to generate He-3 efficiently without producing radioactive materials, using a CNZ alloy to trap and extract He-3, and a heater control unit to maintain the heating element within a predetermined temperature range.
The method achieves efficient production of He-3 without radioactive byproducts, enabling safe and sustainable energy generation with improved thermal energy utilization and no need for radiation shielding, suitable for use in normal industrial facilities.
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Abstract
Description
He-3 manufacturing method, nuclear reaction generating device, and nuclear reaction generating method
[0001] The present invention relates to a method for producing He-3 that does not generate radioactive materials, a nuclear reaction generating device that involves a cold nuclear fusion reaction, and a nuclear reaction generating method.
[0002] Helium (He) exists in the Earth's atmosphere in no small amount (5 x 10 -4 % by volume. However, most of this radiation originates from alpha rays generated during the series decay of natural radioactive isotopes such as underground uranium and thorium, and the isotopes are He-3 (hereinafter also referred to as helium-3) and He-4. He-3 is a valuable element that exists at a ratio of only about one millionth of the He in the Earth's atmosphere, and is an extremely rare stable isotope (a radioactive isotope that does not have radioactivity).
[0003] Traditionally, He-3 was obtained by irradiating lithium (Li) with neutrons to produce tritium (T), a radioactive form of hydrogen, and then waiting a long time (half-life: 12.3 years) for tritium to undergo beta decay into He-3. Neutron irradiation requires the use of nuclear reactors or accelerators, which produces not only tritium but also other radioactive materials. Tritium, the direct raw material, is also radioactive, and there is a risk that it may be mixed into the finished He-3. Tritium decay is one of the current industrial methods for producing He-3.
[0004] Patent Document 1 discloses a helium production method in which a first electrode and a second electrode are immersed in source water containing at least one of tritiated water and heavy water, and a positive voltage pulse is applied to the first electrode, followed immediately by a negative voltage pulse accompanied by a negative pulse current, thereby generating helium in the source water. An electric double layer is formed at the first electrode, creating a state in which a large number of protons and deuterium exist in a narrow space. Accelerated protons collide with deuterium, or protons collide with deuterium in heavy water molecules, resulting in a nuclear fusion reaction between the protons and deuterium, generating He-3. Patent Document 2 also discloses that He-3 is liberated as a reaction product by a low-temperature nuclear fusion reaction involving metals such as palladium and titanium. Both of these He-3 production methods have the problem of generating radioactive materials.
[0005] Additionally, currently practical nuclear power generation uses the energy of nuclear fission to generate electricity. Nuclear fission extracts energy by splitting atomic nuclei such as uranium, while nuclear fusion obtains energy by fusing atomic nuclei. Nuclear fission has problems such as the discharge of radioactive waste in the process, the fact that raw materials such as uranium are finite, and the fact that the fission reaction continues if it becomes uncontrollable. On the other hand, nuclear fusion is expected to be a safe and sustainable energy source because it discharges almost no radioactive waste and the raw material, deuterium, can be obtained from seawater. When nuclear fusion is used to generate electricity, it produces no radioactive waste or carbon dioxide (CO 2 ) can be reduced, fuel can be more easily procured, and safety can be improved.
[0006] Conventional fusion power generation typically produces energy by fusing deuterium (D) and tritium (T). 2No emissions are emitted. Furthermore, nuclear fusion does not experience runaway reactions like those in nuclear power generation, because the nuclear reaction stops when the power source is turned off. However, tritium (T) is a radioactive substance. Furthermore, the 14 MeV neutrons produced during the fusion reaction pose a problem of radioactivity in structural materials. Research and development into energy production through fusion power generation is underway in Japan, with the goal of practical application around 2050. However, one of the reasons for the difficulty in practical application of fusion power generation is the difficulty of plasma control. To fuse atoms, fuel is converted into a plasma state and fused. However, plasma control has been difficult due to issues such as turbulence caused by non-uniformity in the plasma state. For example, magnetic confinement methods, such as tokamak, helical, and field-reversed configuration (FRC), are known to confine the plasma generated by nuclear fusion using a strong magnetic field. Inertial confinement, also known as the laser method, heats fuel particles by irradiating them with laser light.
[0007] Among nuclear fusion methods, cold fusion does not require strong magnetic fields or ultra-high temperatures of tens of millions of degrees Celsius; instead, it initiates fusion at temperatures of around a few hundred degrees Celsius. Typically, cold fusion uses deuterium (D) as fuel, and the final fusion product is helium. This allows fusion to occur even in small devices, making it superior to conventional power generation methods in terms of size and cost. Cold fusion was first announced at the University of Utah in the United States in 1989. Subsequent verification attempts in the United States, Europe, and Japan have not been fully demonstrated. Since then, Japan has been conducting research into "metal-hydrogen thermal reactions" and "condensed matter nuclear science," in which hydrogen is absorbed into metals and stimulated under certain conditions to generate enormous amounts of energy. This research is expected to be put to practical use as a power generator for electric heaters in electric vehicles, among other applications.
[0008] For example, a known heat generating device places a reactant made of a hydrogen-storing metal having a plurality of metal nanoparticles formed on its surface in a reactor with a deuterium gas atmosphere, shortening the internuclear distance between hydrogen atoms in the metal nanoparticles and generating heat stably (see Patent Document 3). Another known heat generating device places a heating element with a multilayer film structure formed on the surface of a base such as a hydrogen-storing metal in a container, introduces a hydrogen-based gas into the container, and heats the heating element with a heater (see Patent Documents 4, 5, and 6, for example). It is also known that a nanocomposite metal material in which Cu and Ni metal particles are supported on a carrier made of Zr (zirconium) with a predetermined oxidation degree generates excess heat of 100 W / kg or more (see Patent Document 7).
[0009] Atmospheric helium, on the other hand, exhibits an abundance of about 1 ppm helium-3, a composition thought to result from primordial nucleosynthesis during the Big Bang. The rarity of helium-3 means that its detection in just a few hundred milligrams of material provides compelling evidence of the occurrence of nuclear reactions, possibly involving the hydrogen fusion process.
[0010] One theoretical model predicting the production of helium-3 is the theory (hereinafter referred to as the 4H / TSC model) that four hydrogen atoms undergo a nuclear fusion reaction inside a metal nanocomposite through tetrahedral symmetric condensation (4H / TSC) (A. Takahashi, "Physics of Cold Fusion by TSC", J. Condensed Matter Nucl. Sci. 12, pp.1-14 (2013), A. Takahashi, "Nuclear Products of Cold Fusion by TSC Theory", J. Condensed Matter Nucl. Sci. 15, pp.1-12 (2014)). The concept of the 4H / TSC model is that when considering the problem of symmetrically arranging four hydrogen atoms and four electrons at the eight vertices of a cube, the electrons and hydrogen atoms are arranged at the shortest distance corresponding to the 12 sides of the cube, resulting in a tetrahedron made by four hydrogen atoms and an accompanying orthogonal tetrahedron made by four electrons. The electrostatic potential of these hydrogen atoms and electrons as point charges results in the smaller the cube, the more stable the hydrogen atoms and electrons are. The quantized Langevin equation is used to explain the dynamic condensation process of the hydrogen atom-electron system. As a result of the weak interaction (electron capture) and the immediately following strong interaction, the hydrogen atom-electron system condenses into an unstable Li * -4 nuclei ( 4 Li * ) and this Li * Two cases are predicted for the decay of the -4 nucleus.
[0011] In the two cases, one is helium 3 ( 3 He) and a proton (p) are produced ( 4 Li * → 3 He + p + 7.72 MeV), the other produces a deuteron (d) and two protons ( 4 Li *→d + 2p + 2.22 MeV). The branching ratio of these two decay processes can be determined experimentally. Rather than continuing the debate over whether the tetrahedral structure occurs as an initial condition within or on the surface of the nanosized Ni crystal lattice, we focus on the detection of helium-3. At this point, the detection of helium-3 would provide evidence in support of the 4H / TSC model. Previous studies have attempted to capture helium-3 as a reaction product of cold fusion.
[0012] Japanese Patent Application Publication No. 2024-65378 Japanese Patent Application Publication No. 03-065689 International Publication Pamphlet WO2015 / 008859 International Publication Pamphlet WO2018 / 230447 International Publication Pamphlet WO2020 / 122097 Japanese Patent Application Publication No. 2023-114385 International Publication Pamphlet WO2021 / 045230
[0013] The inventors verified the hypothesis that helium-3 is trapped inside a Ni-based metal nanocomposite made by adding copper to zirconia, and confirmed the existence of thermal energy (excess heat) obtained from a cold fusion reaction that occurs inside a heating element using hydrogen as fuel. Because the temperature of the heating element strongly influences the progress of a cold fusion reaction, they constructed a structure and control method to maintain the temperature of the heating element as spatially uniform as possible and to extract the obtained thermal energy most efficiently. Furthermore, conventional industrial methods for producing He-3 involve the beta decay of radioactive tritium, which generates radioactive materials during production. This necessitates radiation management and shielding equipment, which places limitations on industrial facilities.
[0014] In view of the above circumstances, the nuclear reaction generating device and the nuclear reaction generating method of the present invention aim to provide a nuclear reaction generating device and a nuclear reaction generating method that are excellent in the utilization efficiency of the thermal energy of a cold nuclear fusion reaction.Furthermore, the He-3 manufacturing method of the present invention aims to provide a He-3 manufacturing method that does not generate radioactive materials.
[0015] To solve the above problems, the nuclear reaction generator of the present invention includes a heating element that induces interactions between hydrogen atoms to generate a nuclear reaction, a container that seals the heating element and hydrogen, and a heater that heats the heating element to a temperature above the reaction initiation temperature at which excess heat is generated. The heating element induces interactions between hydrogen atoms and generates helium-3 inside. The nuclear reaction generator of the present invention is characterized in that helium-3 is generated inside the heating element. The nuclear reaction generator of the present invention further includes a cooling section through which a heat transfer medium (refrigerant) flows that extracts heat from the heating element, and a heater control unit that controls the heater so that the temperature of the heating element does not fall below the reaction initiation temperature but remains within a predetermined temperature range, and so that the spatial distribution of the temperature of the heating element remains within a predetermined range, by controlling the heater so that the temperature of the heating element does not fall below the reaction initiation temperature but remains within a predetermined temperature range, and so that the spatial distribution of the temperature of the heating element remains within a predetermined range. With this configuration, the heating efficiency of the heating element can be improved, and the thermal energy utilization efficiency can be improved by controlling the heater so that the temperature of the heating element remains within a predetermined temperature range but does not fall below the reaction initiation temperature, and so that the spatial distribution of the temperature of the heating element remains within a predetermined range.
[0016] Here, in order to keep the temperature of the heating element as spatially uniform as possible, it is preferable that the heating density of the heater be the same depending on the location of the heater, but it is also acceptable for the heating density to differ depending on the location of the heater. The heating density of the heater can be changed by changing the winding density of the heating wire, for example. In such a case, since the heating density differs depending on the location of the heating element, it becomes easier to control the heater so that the spatial temperature distribution of the heating element falls within a predetermined range.
[0017] In the present invention, the heating element generates thermal energy (excess heat) through a nuclear reaction above the reaction initiation temperature. Because the heating element itself radiates thermal energy, it is necessary for the heater to continue heating the heating element even after it has been heated to the reaction initiation temperature at which excess heat is generated. Furthermore, because the temperature of the heating element decreases due to the heat transfer medium (refrigerant)'s endothermic cooling, the heater must be controlled to maintain the temperature within a predetermined range above the reaction initiation temperature. In other words, the heating element heats up due to the excess heat generated after being heated to the reaction initiation temperature and the heat generated by the heater, but the heater must be controlled so that the temperature does not fall below the reaction initiation temperature due to the heat dissipation from the heating element itself and the heat transfer medium (refrigerant)'s endothermic cooling. The lower limit of the predetermined temperature range is set several tens of degrees Celsius above the reaction initiation temperature, taking into account the temperature drop due to the heat transfer from the heating element and the heat transfer medium (refrigerant)'s endothermic cooling. Furthermore, because the nuclear reaction occurs within the solid interior of the heating element, the upper limit of the predetermined temperature must be below the melting point of the heating element.
[0018] Next, the method for generating a nuclear reaction of the present invention involves sealing a heating element and hydrogen in a container, inducing interactions between hydrogen atoms using the heating element to generate a nuclear reaction and producing helium-3 inside. By cooling the container so that at least a portion of the heating element is within a predetermined temperature range, a method for generating a nuclear reaction with higher energy efficiency can be provided. Alternatively, the heating element may be heated while the container is cooled so that at least a portion of the heating element is within a predetermined temperature range. This increases the heat generation efficiency of the heating element and improves the efficiency of thermal energy utilization. The method for generating a nuclear reaction of the present invention satisfies at least one of the following formulas 1 and 2. (Formula 1) Energy produced by the method for generating a nuclear reaction > Nuclear fusion energy released when helium-3 is generated from hydrogen. (Formula 2) 1 / 100 < Nuclear fusion energy released when helium-3 is generated from hydrogen / Energy produced by the method for generating a nuclear reaction < 1 / 2. Furthermore, an intermediate exists in the process of generating helium-3 from hydrogen.
[0019] The present invention also provides a method for producing He-3 by calcining an amorphous alloy (hereinafter also referred to as a CNZ alloy) composed of copper (Cu), nickel (Ni), and zirconium (Zr) at 400 to 500°C, pulverizing the alloy, absorbing hydrogen, and further calcining the resulting alloy oxide at 400 to 500°C. The calcined alloy compound is then heated to 900°C or higher to extract the He-3 held in the alloy oxide. The inventors discovered that by subjecting a CNZ alloy to a specific treatment to absorb hydrogen and then calcining the alloy, He-3 remains stably within the alloy, leading to the completion of the present invention. He is an inert rare gas with a small atomic size, but rather than clinging to the idea that it easily escapes from solids into a gas, they believed that it remains stably within the solid. This is because He atoms present between the lattices of perfect crystals can easily move, but when they are trapped in lattice defects such as vacancies, they do not easily escape, and perfect crystals do not exist.
[0020] After firing the CNZ alloy at 400 to 500°C, the alloy oxide contains a larger amount of Zr in the composition ratio, and the zirconia (ZrO 2 ) can be considered to be a dispersion of Ni and Cu alloys. ZrO is a ceramic material, which is different from metals. 2 Regarding this, if the crystal structure is well-ordered, it is believed that approximately 100% of He-3 will remain within the alloy oxide if the temperature is raised to 400 to 500°C. By heating the alloy oxide to 900°C or higher, the He-3 remaining within the alloy oxide is extracted into the external gas.
[0021] In the method for producing He-3 of the present invention, the alloy oxide in which hydrogen has been absorbed is preferably heated to 1400°C or higher in a nitrogen or argon atmosphere to extract He-3. 2 Since Ni and Cu are dispersed in the He-3, the efficiency of extracting He-3 can be improved by heating it to a temperature close to the melting point of Ni (1455°C) (the melting point of Cu is 1085°C).
[0022] In the method for producing He-3 of the present invention, it is preferable that He-3 is released into the ambient gas and then concentrated or separated and purified. Because He has a low boiling point, for example, by lowering the gas temperature, it is possible to identify He as the gas that remains until the end.
[0023] Here, the composition ratio of Cu:Ni:Zr in the amorphous alloy is preferably 1:5 to 12:10 to 24. In the composition ratio of Cu:Ni:Zr, the composition ratio of Cu is the lowest, and the composition ratio of Ni is 5 to 10 times that of Cu. In addition, in the alloy oxide, the zirconia (ZrO 2 It is preferable that the composition ratio of Cu:Ni:Zr is even higher than that of Ni. If the ratio of Cu to Ni changes and falls outside the range of 1:5 to 1:12, or if the ratio of Ni to Zr changes and falls outside the range of 5:10 to 5:24, i.e., 1:2 to 1:4.8, the reaction to produce He-3 is difficult to occur, and these are not appropriate composition ratios.
[0024] In the present invention, He-3 is generated as one of the products of the nuclear fusion reaction inside the alloy oxide. 2The process by which He-3 is produced when hydrogen is absorbed into a CNZ alloy oxide, in which a Ni-Cu alloy is dispersed, can only be considered a nuclear fusion reaction. As will be described later, the theory that four protons condense in a CNZ alloy into a tetrahedral symmetric condensate (4H / TSC) in a CNZ alloy has been proven (A. Takahashi, "Physics of Cold Fusion by TSC", J. Condensed Matter Nucl. Sci. 12, pp. 1-14 (2013), A. Takahashi, "Nuclear Products of Cold Fusion by TSC Theory", J. Condensed Matter Nucl. Sci. 15, pp. 1-12 (2014)). The nuclear fusion reaction generates reaction heat through a metal hydrogen energy reaction (MHE), which can be used as a secondary heat source in the He-3 production process of the present invention.
[0025] A second aspect of the present invention is a method for producing He-3, which involves calcining an amorphous alloy consisting of Pd (palladium), Ni, and Zr at 400 to 500°C, pulverizing it, allowing hydrogen to be absorbed, and then calcining the alloy oxide with the absorbed hydrogen at 400 to 500°C. The calcined alloy oxide with the absorbed hydrogen is then heated to 900°C or higher, thereby extracting the He-3 held in the alloy oxide. CNZ alloy oxide (Cu—Ni / ZrO 2 He-3 can be produced using materials other than PNZ alloy oxide (Pd-Ni / ZrO 2 ) is one of them. In addition, in these alloy oxides, the base material ZrO 2 to silica (SiO 2 ) (also called CNS alloy oxide and PNS alloy oxide, respectively), that is, He-3 can also be produced by replacing Zr in the composition of CNZ alloy or PNZ alloy with Si (silicon).
[0026] The above-mentioned CNZ alloy oxide, PNZ alloy oxide, CNS alloy oxide, and PNS alloy oxide, which have hydrogen stored therein and are used in the method for producing He-3, are hydrogen storage alloy oxides that retain He-3 and from which He-3 can be extracted by a predetermined temperature-raising treatment. These hydrogen storage alloy oxides are capable of stably storing He-3.
[0027] According to the nuclear reaction generating device and nuclear reaction generating method of the present invention, a room temperature nuclear fusion reaction can be caused inside a heating element, thereby increasing the heat generation efficiency of thermal energy from the heating element and improving the efficiency of energy utilization.
[0028] Furthermore, the method for producing He-3 of the present invention has the advantage that it does not generate radioactive materials during production. Furthermore, since it does not generate radioactive materials, there is no need for radiation control or shielding equipment, and there are no restrictions on industrial facilities, so that it can be produced in a normal industrial facility.
[0029] Schematic diagram of the nuclear reaction generator (Example 1) Schematic diagram of the demonstration test device Graph showing scattering behavior Graph showing proton production behavior Schematic diagram of the operating principle of an etching-type track detector Optical microscope photograph of etch pits on a solid-state track detector Heat generation amount of the sample and number density of etch pits recorded on the solid-state track detector Helium 3 and H from the sample 3 + (both m / e = 3) Graph showing the correlation between the water signal from the sample and the signal of mass 3 Diagram of nuclear fusion efficiency Graph of nuclear reaction efficiency obtained by changing the number of times the sample was re-fired (fired in air after hydrogen experiments) Cross-sectional view of the container of the nuclear reaction generator Graph showing the temperature difference between the sample temperature and the calibration zirconia beads Correlation diagram between hydrogen gas pressure and excess heat (ΔT) Schematic diagram of the configuration of the nuclear reaction generator (Example 2) Schematic diagram of the configuration of the nuclear reaction generator (Example 3) Schematic diagram of the configuration of the nuclear reaction generator (Example 4) Cross-sectional view 1 of the container of the nuclear reaction generator (Example 5) Cross-sectional view 2 of the container of the nuclear reaction generator (Example 5) Production flow diagram of He-3 (Example 6) Explanatory diagram of an example of the production process of He-3 (Example 6)
[0030] An example of an embodiment of the present invention will be described in detail below with reference to the drawings. Note that the scope of the present invention is not limited to the following examples and illustrated examples, and many modifications and variations are possible.
[0031] Fig. 1 is a schematic diagram of one embodiment of the nuclear reaction generator of the present invention. The nuclear reaction generator 1 shown in Fig. 1 is composed of a heating element 4 that induces interactions between proton atoms to generate a nuclear reaction, a container 3 that seals the heating element 4 and hydrogen gas 8, a heater 5 that heats the heating element 4 to a temperature above the reaction initiation temperature at which excess heat is generated inside the heating element 4, a cooling unit 2 in which a heat transfer medium (refrigerant) flows around the container 3 to extract heat from the heating element 4, a hydrogen gas tank 11 that supplies hydrogen gas 8, thermocouples (6a, 6b) as temperature sensors, and a heater control unit 12 that controls the heater based on the temperature of the heating element 4 measured by the thermocouple 6a.
[0032] When the heating element 4 in the nuclear reaction generator 1 is heated by the heater 5 to a temperature equal to or higher than the reaction initiation temperature, it induces an interaction between proton atoms and generates helium 3 inside. The heater control unit 12 controls the heater so that the temperature of the heating element 4 falls within a predetermined temperature range and does not fall below the reaction initiation temperature due to a temperature drop caused by heat radiation from the heating element 4 and heat absorption by the heat transfer medium 7, and so that the spatial temperature distribution of the heating element 4 falls within a predetermined range. In the description of the examples in this specification, proton gas may be simply referred to as hydrogen gas.
[0033] The cooling unit 2 contains a heat transfer medium 7, and is provided with an inlet 21 and an outlet 22 for the heat transfer medium 7, which circulates around the periphery of the container 3 and extracts heat from the heating element 4 via the container 3. Inside the container 3, there are provided, in order from the inside out, a heater 5, a heating element 4, and a storage space for hydrogen gas 8, which are sealed by the container 3. A hydrogen gas tank 11 functions as a supply unit that supplies hydrogen gas 8 to the container 3, and is connected to the container 3 by a pipe 15. A valve 14 is provided on the pipe 15, which allows the supply of hydrogen gas 8 to the container 3 to be adjusted. Pressure gauges (13a, 13b) measure the hydrogen gas pressure in the tank or pipe, and the pressure gauge 13a is attached to the hydrogen gas tank 11, and the pressure gauge 13b is attached to the pipe 15.
[0034] The heating element 4 induces the interaction between atoms of hydrogen gas to generate a nuclear reaction, and may be, for example, an amorphous alloy composed of Cu (copper), Ni (nickel), and Zr (zirconium), or an alloy compound (Cu-Ni / ZrO 2 system, Pd-Ni / ZrO 2 It is a Cu-Ni / ZrO metal nanocomposite. 2 system and Pd-Ni / ZrO 2 In addition to the metal nanocomposite of the above system, Cu-Ni / SiO 2 Pd—Ni / SiO 2 A metal nanocomposite of this type can also be used as a heating element. The heating element 4 is provided so as to surround the heater 5, and the heating element 4 is further surrounded by and fixed to a highly breathable and heat-resistant metal mesh, such as a stainless steel mesh 40. The amorphous alloy may be pulverized into particles or powder. The particle size is 1 mm or less, preferably 0.5 mm or less, and the average particle size is preferably in the range of 0.05 to 0.3 mm.
[0035] The heater 5 heats and maintains the heating element 4 at a predetermined temperature or higher. The heater 5 is connected to a heater control unit 12 and is temperature-controlled by the heater control unit 12. The thermocouple 6a is introduced inside the heating element 4, and the thermocouple 6b is introduced inside the container 3. Therefore, the thermocouple 6a measures the temperature of the heating element 4, and the thermocouple 6b measures the temperature of the hydrogen gas 8 filling the container 3. The heater control unit 12 controls the heater 5 based on the temperature data acquired from the thermocouples (6a, 6b) so that at least a portion of the heating element 4 is within a predetermined temperature range. Furthermore, the heat medium 7 circulates within the cooling unit 2, thereby exchanging heat with the container 3 and with water in an external water reservoir, thereby forming a heat cycle. Furthermore, helium 3 is produced inside the heating element 4 due to a nuclear reaction occurring in the heating element 4.
[0036] The vessel 3 may have any of the following shapes: a hollow cylindrical shape with a bottom, a hollow spherical shape, a hollow prismatic shape with a bottom, and a spiral shape formed from a hollow cylindrical shape with a bottom. For example, a hollow spherical shape facilitates thermal design within the device due to the high symmetry of the vessel shape. Furthermore, a hollow cylindrical shape with a bottom that is spiraled further ensures a longer area for nuclear reactions to occur, resulting in a more energy-efficient nuclear reaction generator. The vessel 3 is preferably made of a metal that is resistant to high-temperature oxidation and has high heat resistance, such as stainless steel. For example, SUS304, which contains 18% chromium and 8% nickel, is used. The vessel 3 is sealed because hydrogen reacts with oxygen and undergoes a chemical reaction when exposed to the outside air. Sealed refers to the fact that the heating element and hydrogen do not come into contact with the outside air, or that even if they do, the amount of contact is negligible.
[0037] The cooling unit 2 is filled with a heat transfer medium (refrigerant) such as water or oil, and piping is provided to circulate the heat transfer medium (refrigerant). The piping may include a piping having both a portion where the heat transfer medium (refrigerant) absorbs heat through heat exchange with a heat generating element and a portion where the heat transfer medium (refrigerant) releases heat through heat exchange with the outside. This allows the piping to serve as both a portion constituting a heat cycle. In such a case, by having a portion where heat is released through heat exchange with the outside, the piping can serve as a flow path for the heat transfer medium (refrigerant) and a portion constituting a heat cycle. The cooling unit 2 may be disposed outside the container 3 or inside the container 3.
[0038] The nuclear reaction generator 1 may further include a supply unit that supplies hydrogen gas into the container. The supply unit that supplies hydrogen gas into the container allows for easy replenishment of the hydrogen gas in the container. The supply unit preferably includes a hydrogen cylinder that stores hydrogen gas and a supply port for introducing hydrogen gas from the hydrogen cylinder into the container. This allows for stable storage of hydrogen gas and for supplying hydrogen gas into the container via the supply port as needed. The supply unit may also include a cassette-type hydrogen cylinder that is detachable from the container because hydrogen loss is minimal. This allows for stable storage of hydrogen gas and for supplying hydrogen gas into the container via the supply port as needed. Furthermore, the supply unit may include a liquefied hydrogen cylinder that stores liquid hydrogen and a liquefied hydrogen supply port for introducing hydrogen from the liquefied hydrogen cylinder into the container. This allows for stable storage of hydrogen gas and for supplying hydrogen gas into the container via the supply port as needed. The supply amount of hydrogen gas 8 (i.e., the flow rate through the piping of the supply unit) is controlled so that the temperature of the heating element 4 is within a predetermined temperature range. This also improves the heat generation efficiency of the heating element 4. Temperature control can be made easier by controlling the flow rate of the hydrogen gas 8 in the piping together with the heater 5 so that the temperature of the heating element 4 falls within a predetermined temperature range.
[0039] The nuclear reaction generator 1 may further include a heat retaining section that prevents heat dissipation from the heating element 4. By including a heat retaining section that makes it difficult for heat generated from the heating element 4 to dissipate to the outside, it becomes easier to maintain at least a portion of the heating element within a predetermined temperature range. This makes it possible to obtain a nuclear reaction generator with higher energy efficiency.
[0040] In the nuclear reaction generator 1, when viewing any cross section of the container 3, there may be a portion where the heater 5, the heating element 4, and the container 3 are arranged in this order. When viewing any cross section, there is a portion where the heater 5, the heating element 4, and the container 3 are arranged in this order. Since the heater 5 and the heating element 4 are spatially close in that portion, the heat generated by the heater 5 is easily transferred to the heating element 4, making it easy to heat up. Furthermore, since the heating element 4 and the container 3 are spatially close, the heat generated by the heating element is easily extracted to the outside of the container 3. If hydrogen gas 8 is arranged around any of the heating elements 4, when viewing any cross section of the container 3, there is a portion where the heater 5, the heating element 4, the hydrogen gas 8, and the container 3 are arranged in this order. In the portion where the heater 5 and the heating element 4 are arranged in this order, the heater 5 and the heating element 4 are spatially close in that portion, making it easy for the heater to heat the heating element. Furthermore, since the hydrogen gas 8 is present between the heating element 4 and the container 3 and they are in indirect contact, it is easy to keep the container 3 below its heat-resistant temperature even if the heating element 4 becomes hot.
[0041] In the nuclear reaction generator 1, the reaction initiation temperature is higher than 300°C, up to 350°C. By raising the temperature above 300°C, the heating element 4 generates thermal energy (excess heat) through a nuclear reaction. Since the heating element 4 itself radiates thermal energy, it is necessary for the heater 5 to continue heating the heating element 4 even after the heating element 4 has been heated to the reaction initiation temperature at which excess heat is generated. Furthermore, since the temperature of the heating element 4 drops due to the heat transfer medium (refrigerant) 7 absorbing heat, it is necessary to control the heater 5 so that the temperature remains within a predetermined range above the reaction initiation temperature. In the future, it will be possible to improve the effective nuclear reaction conversion efficiency (ε eff ), it may be possible to maintain the heating element 4 at a temperature higher than the reaction initiation temperature even after the heater 5 is turned off, due to spontaneous heat (excess heat) generated by the nuclear reaction in the heating element 4. In this case, the heating of the heating element 4 by the heater 5 only functions as a starter for the nuclear reaction, and there is no need to continue heating the heating element 4 by the heater 5. In other words, in a nuclear reaction generating device, if the heating element can be maintained at a temperature higher than the reaction initiation temperature by spontaneous heat (excess heat) generated by the nuclear reaction even after the heater is turned off, the effective nuclear reaction conversion efficiency (ε eff) the heater control unit turns off the heater and stops heating the heating element, thereby improving energy efficiency.
[0042] The predetermined temperature range is set to 350 to 400°C, with the lower limit being equal to or higher than the reaction initiation temperature, taking into consideration the temperature drop due to heat radiation from the heating element 4 and heat absorption by the heat transfer medium (refrigerant) 7. Furthermore, the upper limit temperature must be lower than the melting point of the heating element 4, since the nuclear reaction occurs inside the solid heating element 4. A preferred upper limit temperature is a temperature set based on the heat resistance temperature for quality assurance of the container 3 and lower than the melting point of the heating element 4, specifically 900 to 1450°C, more preferably 550 to 800°C, and even more preferably 550 to 600°C. The predetermined temperature range is set within the range of 350 to 1450°C, equal to or higher than the reaction initiation temperature, and is determined from the perspective of the melting point of the heating element 4, the heat resistance temperature for quality assurance of the container, and energy efficiency.
[0043] The nuclear reaction generator 1 may further include a pressure control unit that controls the pressure inside the container 3, thereby controlling the degree of nuclear reaction occurrence in the heating element 4. Since the degree of nuclear reaction occurrence in the heating element 4 varies depending on the pressure of the hydrogen gas 8 sealed in the container, the heat generation efficiency of the heating element 4 can be increased by controlling the pressure inside the container. Therefore, a nuclear reaction generator with higher energy efficiency can be obtained. Note that, according to the 4H / TSC model, the following can be theoretically derived. That is, there is a first pressure range in which the occurrence of nuclear reactions in the heating element 4 increases with an increase in the pressure of the hydrogen gas 8 sealed in the container, and a second pressure range in which the occurrence of nuclear reactions in the heating element decreases with an increase in the pressure of the hydrogen gas 8 sealed in the container. In other words, there is a first pressure range in which the occurrence of nuclear reactions in the heating element 4 increases, and a second pressure range in which the occurrence of nuclear reactions in the heating element 4 decreases. Therefore, by controlling the pressure of the hydrogen gas 8, the heat generation efficiency of the heating element can be increased, and the utilization efficiency of the thermal energy of the heating element can be improved.
[0044] From the above, in the nuclear reaction generating device, as the pressure of the hydrogen gas sealed in the container increases, there is a first pressure range in which the occurrence of nuclear reactions in the heating element increases, and a second pressure range in which the occurrence of nuclear reactions in the heating element decreases, and there is also a pressure range in which the occurrence of nuclear reactions switches from increasing to decreasing, and the pressure control unit controls the pressure inside the container to within the pressure range in which the occurrence of nuclear reactions switches from increasing to decreasing, thereby controlling the degree of occurrence of nuclear reactions in the heating element.
[0045] When the nuclear reaction generator 1 includes a pressure control unit, the pressure inside the vessel may be controlled within a range of 0.1 to 1 MPa. Note that, in this specification, the term "pressure" refers to absolute pressure, which is pressure expressed relative to an absolute vacuum (complete vacuum), and not to gauge pressure, which is expressed relative to the ambient pressure. According to the findings of the 4H / TSC model, as the pressure of the hydrogen gas 8 sealed inside the vessel is increased, a peak appears in the rate of nuclear reaction generation in the heating element 4. Therefore, by controlling the pressure inside the vessel within a range of 0.1 to 1 MPa, the heat generation efficiency of the heating element 4 can be increased, resulting in a nuclear reaction generator with higher energy efficiency. Furthermore, in the nuclear reaction generator 1, the actual consumption rate of the hydrogen gas 8 is slower than the hypothetical consumption rate of protons when it is assumed that all of the energy produced in the nuclear reaction generator 1 is generated by nuclear fusion reactions.
[0046] In the nuclear reaction generator 1, the heating element 4 preferably includes a storage material capable of absorbing hydrogen gas 8. A nuclear reaction can be generated by inducing interactions between hydrogen atoms within the storage material. This allows for the realization of a practical nuclear reaction generator. The storage material may be a granular material. When the storage material is granular, the contact area between the storage material and hydrogen can be increased, allowing for more efficient inducing interactions between hydrogen atoms and generating a nuclear reaction. In the case of a granular material, the particle size is 1 mm or less, preferably 0.5 mm or less, and the average particle size is preferably in the range of 0.05 to 0.3 mm. This allows for a nuclear reaction generator with higher energy efficiency. The storage material may be a material sintered into a predetermined shape. When the storage material is sintered into a predetermined shape, it is easy to maintain the occlusion material in the predetermined shape, and an occlusion material that is easy to handle can be obtained. This allows for a nuclear reaction generator with higher operability.
[0047] The surface temperature of the vessel 3 in the nuclear reaction generator 1 is preferably 150°C or higher and 280°C or lower. This allows a nuclear reaction to be continuously generated in the heating element 4 within a range that maintains the heat resistance of the vessel 3. Note that this temperature condition is for when SUS304 is used as the material for the vessel 3. If a material with excellent heat resistance, such as Inconel (a registered trademark of Special Metals Corporation) or Hastelloy (a registered trademark of Haynes Corporation), is used as the material for the vessel 3, the above temperature condition can be made even higher.
[0048] In the nuclear reaction generator 1, the reaction between hydrogen atoms is induced and helium 3 is generated inside the heating element 4. Helium 3 is generated inside the heating element, and the thermal energy resulting from this nuclear fusion reaction is efficiently utilized.
[0049] The nuclear reaction generator 1 satisfies at least one of the following formulas 1 and 2: (Formula 1) Energy produced by the nuclear reaction generator > Nuclear fusion energy released when helium-3 is produced from hydrogen. (Formula 2) 1 / 100 < Nuclear fusion energy released when helium-3 is produced from hydrogen / Energy produced by the nuclear reaction generator < 1 / 2.
[0050] In the nuclear reaction generator 1, the heater is controlled so that the temperature of the heating element is within a predetermined temperature range, but in addition, the heat generation efficiency of the heating element can be improved by controlling the cooling section through which the heat transfer medium (refrigerant) that extracts heat from the heating element flows. That is, the amount and flow rate of the heat transfer medium (refrigerant) are controlled to increase or decrease the amount of heat (amount of heat absorbed) extracted from the heating element. Temperature management can be made easier by controlling the cooling section together with the heater so that the temperature of the heating element is within a predetermined temperature range.
[0051] (Demonstration of cold fusion reaction) The inventors confirmed that when a heating element is heated by a heater above the reaction initiation temperature, helium 3 is generated by the nuclear fusion reaction, and that excess heat is generated in excess of the heating of the heater. The sample used as the heating element was Cu-Ni / ZrO, which was made by sintering an amorphous alloy composed of Cu, Ni, and Zr, allowing it to absorb hydrogen, and then sintering it again. 2 This metal nanocomposite is based on the CNZ system. In this specification, this metal nanocomposite will be referred to as CNZ oxide. Thermal desorption spectrometry (TDS) and nuclear reaction analysis (NRA) were used as analytical methods. TDS involves heating a sample at a constant rate in a vacuum and measuring the partial pressure of the thermally released helium gas using a mass spectrometer. On the other hand, NRA utilizes the nuclear reaction between a diagnostic beam accelerated to high energy and a target isotope in the sample. NRA is an analytical method that can be said to be optimal for helium-3, and utilizes the nuclear reaction between deuterons accelerated to high energy and helium-3. The nuclear reaction equation is d+ 3 He → 4 He + p., which produces alpha rays and protons. The protons, in particular, have an energy of about 14 MeV and are easily emitted from the sample being analyzed, so they can be measured with a radiation detector.
[0052] Figure 2 shows a schematic diagram of a demonstration test device. It has the same configuration as the nuclear reaction generator shown in Figure 1, but the cooling section 2 has been replaced with a cylindrical insulated container made of SUS304, and the inside of the insulated container is a vacuum 102. The inventors have confirmed using TDS that, for Ni, 20 keV helium ions with a range of 0.1 μm are captured almost 100% at room temperature at low fluence, but most are released to the outside when the temperature is raised to about 1050°C. It has also been confirmed that for Cu, helium injected at a temperature raised to about 950°C is released almost 100%. In this way, when the fluence is raised to 10 17 ions / cm 2 If it is below Cu—Ni / ZrO 2 Even when the temperature of the metal nanocomposite is raised to about 500°C, Ni and Cu stably retain helium inside. 2 It is known that about half of the helium 3 is lost outside the CNZ oxide when the temperature rises to 830°C. 2 Regarding the metal nanocomposite, since it is a ceramic, there is room for further investigation into the effects of microcracks, etc., but if the crystal structure is well-ordered, approximately 100% of the 3He will remain inside the metal nanocomposite if the temperature is raised to about 500°C. It can be inferred that even after heating, at least in the metal phase, almost all of the generated 3He will remain inside the metal nanocomposite.
[0053] In the actual analysis, the temperature of the TDS was raised from room temperature to 1200°C at a constant rate of 10°C / min, and the partial pressure at that time was measured using a quadrupole mass spectrometer (PrismaPro QMG250M2, Pfeiffer Vacuum, Germany) and recorded as a function of temperature. An infrared heating device manufactured by Thermo Riko was used for heating, and heating of anything other than the sample and its holder was avoided as much as possible (GVL298, THERMO RIKO, Japan). The amount of CNZ oxide used for the analysis was approximately 0.1 g for both TDS and NRA. The signal of helium-3 appears in mass-3, but due to the influence of residual gas, H is not detected in the ion source of the mass spectrometer. 3 +However, the heat release behavior from the sample to the vacuum is chemically very different between hydrogen and helium (temperature dependence is different). 3 + Is H 2 and hydrogen atoms (H or H + ) are produced by the reaction, so H and H 2 , H 2 The signal from helium-3 correlates with the signal from O. On the other hand, the signal from helium-3 does not correlate with these hydrogen-containing molecular species. Therefore, signals related to hydrogen, such as mass-1, mass-2, and mass-18, were also recorded to confirm the correlation.
[0054] For the NRA, the M-15 line of the tandem electrostatic accelerator 5SDH-2 at the Accelerator and Particle Beam Experimental Facility attached to the Kobe University Graduate School of Maritime Sciences was used, and the deuteron energy used for the analysis was 1.4 MeV. Each sample was irradiated for 5 hours at a current value of 5 nA, and the protons generated were measured and recorded using a highly sensitive solid-state track detector.
[0055] The metal nanocomposite is in powder form and is held in a vacuum. To do this, a 9x9mm fluorescent screen is placed on the beam monitor. 2 The sample was sandwiched between thin Kapton films (7.5 μm thick) and fixed in place. Two solid-state track detectors were stacked, and the surface facing the sample was shielded from light with aluminum foil. By stacking two solid-state track detectors and measuring the surface of the second one, only protons of 10 MeV or higher can be identified and measured. The radiation behavior calculation code (PHITS: Particle and Heavy Ion Transport code System), a Monte Carlo calculation code, was used to design the irradiation and analysis system, and it was optimized. Quantitative analysis of helium-3 in the sample was performed based on the number of etch pits measured.
[0056] Figure 3 is a graph showing the scattering behavior of 1.4 MeV deuterons by CNZ oxide, and represents the results of the PHITS simulation of the interaction between a 1.4 MeV deuteron beam and a sample. The deuteron beam scattered by the sample has a certain degree of divergence, but it is possible to position a solid-state track detector to avoid this.
[0057] Figure 4 is a graph showing the proton production behavior from CNZ oxide upon irradiation with 1.4 MeV deuterons. It represents the results of the reaction between 3He and deuterons in a sample irradiated with 1.4 MeV deuterons, as simulated by PHITS. The generated protons were positioned so that they could be perpendicularly incident on the solid-state nuclear track detector. In this calculation, we assumed that the amount of 3He in the CNZ oxide was equal to the amount of Cu, and emphasized the amount of protons produced. The solid-state nuclear track detector was etched for 5 hours using a 6M KOH solution maintained at 70°C. Etch pits were observed using an optical microscope (Keyence VHX-5000) at the Kobe University Research Infrastructure Center, Isotope Division.
[0058] The results of the NRA and TDS, which demonstrated successful quantitative analysis, are shown below. Table 1 below lists the samples used in the analysis (including each sample's composition ratio, processing and experimental history, and calorific value). Each sample was prepared by air-sintering amorphous alloys of Cu, Ni, and Zr, but the composition ratios differed depending on the sample. After the initial hydrogen exothermic reaction, air-sintering and hydrogen exothermic reactions were repeated multiple times. Some samples were analyzed at different times, resulting in clear differences in total calorific value. The amount of 3He retained in each sample also varied depending on the calorific value. Regarding the processing and experimental history, A represents calcination at 450°C for 60 hours, grinding, and hydrogen exothermic reaction; B represents air-sintering at 450°C for 180 hours; and C represents hydrogen exothermic reaction.
[0059] Here, the preparation of the sample will be explained. First, an amorphous alloy with a composition of Cu, Ni, and Zr is prepared based on a preset composition ratio. Next, the amorphous alloy is fired in the air at 400 to 500°C. The amorphous alloy is heated to, for example, 450°C in a crucible to oxidize it. The firing time depends on the amount of alloy, but is typically 20 to 100 hours, for example, 60 hours. This oxidation converts Zr into ZrO. 2 Here, the oxidation causes some Cu to be oxidized to produce copper oxide, but almost no Ni is oxidized. The oxidized CNZ oxide is pulverized to obtain fine CNZ oxide. The pulverization can be carried out automatically, for example, in a mortar. The particle size of the CNZ oxide after pulverization is 1 mm or less, preferably 0.5 mm or less, and the average particle size is preferably in the range of 0.05 to 0.3 mm.
[0060] Hydrogen is absorbed into the obtained fine CNZ oxide. To absorb hydrogen into the fine CNZ oxide, hydrogen gas (light hydrogen) is supplied to the CNZ oxide in a sample container placed in a reaction vessel under vacuum. Hydrogen absorption is carried out for several hours or more at approximately 4 atmospheres and 400-500°C. For example, hydrogen is absorbed into the CNZ oxide at 0.4 MPa and 450°C for 5 hours. The pulverized CNZ oxide is then calcined in the air at 400-500°C for 100-250 hours. Calcination in the air may be repeated.
[0061]
[0062] Samples 1 and 2 were prepared with a Cu:Ni:Zr composition ratio of 1:10:20, while samples 3 and 4 had a composition ratio of 1:7:14. The details of each of the treatments A, B, and C in the treatment and experimental history are as described above. All samples 1 to 4 underwent treatment A, B, and C, and samples 1 to 3 also underwent a set of treatment B and C once or twice. Sample 4 also underwent repeated treatment C twice. Comparing samples 2 and 3, which had the same treatment and experimental history but different composition ratios, there was a difference in the total heat generated by the hydrogen exothermic reaction. Furthermore, after treatments A, B, and C were performed, differences in the total heat generated were confirmed even though the treatment histories were different.
[0063] A solid-state nuclear track detector was used to measure protons at the NRA. By recording the latent tracks of protons as tiny etch pits on the solid-state nuclear track detector, it is possible to reliably measure and identify individual protons. When protons with energies of 10 MeV or less are incident almost perpendicularly, the solid-state nuclear track detector has literally 100% detection efficiency, so the etch pits could be reliably determined to be protons based on their geometric shape and growth behavior due to additional etching treatment.
[0064] The operating principle of the track detector is shown in Figure 5. It shows the case where two types of ions penetrate the detector. The track etching rate V along the latent track of the ions is t The bulk etching rate V proceeds from the other surfaces. b Since the ion energy is larger than the Bragg peak, etch pits of different geometric shapes and sizes are created depending on the ion charge and energy. In the case of protons, at energies higher than the Bragg peak, the damage density of the latent tracks decreases, so the track etching rate decreases and, as a result, the etch pits become smaller. Strictly speaking, the etch pits are not conical because the track etching rate changes with depth.
[0065] Figure 6 is an optical microscope photograph of the surface of the solid-state nuclear track detector after etching, showing the results of the NRA analysis for sample No. 3. The starting material for the metal nanocomposite of sample No. 3 is an amorphous alloy with a Cu:Ni:Zr ratio of 1:7:14. After the initial firing (450°C, 180 hours) and grinding, a hydrogen exothermic reaction was carried out, followed by air re-firing (450°C, 60 hours) and three repeated hydrogen exothermic reactions. The total heat generation was 5.5 x 10 4 J / 0.1 g. The etch pit density on the solid-state nuclear track detector was 1,113±23 pits / cm 2 It was.
[0066] In Figure 6, several etch pits of different sizes are observed, and all of them were determined to be proton etch pits generated by the nuclear reaction of deuterium with helium-3. Etch pits similar to those shown in Figure 6 were also observed in the CNZ oxides of sample numbers 1 and 2. This clearly shows that helium-3 was generated in the CNZ oxides by the nuclear fusion reaction.
[0067] Figure 7 shows the relationship between the total heat release during the hydrogen exothermic reaction and the number density of etch pits recorded on the solid-state nuclear track detector for these samples. The hydrogen exothermic reaction was performed multiple times using CNZ oxide, with different amounts of CNZ oxide loaded into the reaction vessel and exposed to hydrogen for each run. The heat release shown here is the total heat release converted to per 0.1 g of CNZ oxide. It can be seen that the density of etch pits increases in almost proportion to the excess heat. Furthermore, the best-fit line for the three experimental points passes almost through the origin. This means that there is almost no influence other than the 3He generated by the hydrogen exothermic reaction.
[0068] According to calculations using PHITS simulations, the number of protons (10-16 MeV) expected to reach the solid-state nuclear track detector and the measured density of etch pits indicate that the CNZ oxide of sample 3 contains approximately 5.0 x 10 15 It is estimated that 5 x 10 helium-3 were produced. 15 If helium-3 is produced, the resulting heat generation is 6.2 x 10 3 J / 0.1 g, which is an order of magnitude lower than the measured excess heat. 2 It is speculated that this is due to the high mobility of the helium-3 present in the sintered body, which is lost to the outside of the system during firing, or the branch effect of deuterium production. However, it is also possible that nuclear fission reactions of atomic nuclei such as Ni, Cu, and Zr are also occurring at the same time.
[0069] Figure 8 shows the thermal release curve of the molecular species detected as a signal with mass number 3 from CNZ oxide. The horizontal axis represents the temperature measured by a thermocouple in contact with the top surface of the sample or sample dish, and the vertical axis represents the output of helium 3 and H 3 +In this system, the signals from both HD + (protium and deuterium molecular ions) and T + The possibility of hydrogen ions (tritium ions) can be excluded with sufficient evidence. The focus is on the release in the temperature range above 900°C. The signal from the sample dish alone and the CNZ oxide before the hydrogen exothermic reaction also increases, but the signal from the CNZ oxide after the hydrogen exothermic reaction has a higher value. The main hydrogen gas H 2 The emission of HCl almost subsides up to 800°C, but becomes significant again above 900°C.
[0070] From the results of thermal desorption analysis of helium ions implanted into Cu and Ni, it is believed that helium 3 is released in this temperature range. On the curve after the hydrogen exothermic reaction, a high release peak from 20 to 100°C and a broad release peak from 100 to 600°C are also seen. These are hydrogen molecules H 2 It was confirmed that there was a good correlation with the signal (m / e=2) of H 2 is decomposed in the ion source of the mass spectrometer to produce H + and H 2 The reaction is H 3 + On the other hand, the emission signal in the temperature range above 900°C is H 2 There is little correlation with 3 + It has become clear that it is difficult to attribute
[0071] As shown in FIG. 2 When examining the correlation with the O (m / e = 18) signal, the signal emitted above 800°C showed a good correlation with the water signal for the sample dish alone and the sample (CNZ oxide before the hydrogen exothermic reaction). In contrast, the signal from the sample (CNZ oxide after the hydrogen exothermic reaction) increased independently of the increase in the water signal as the temperature increased, and showed an inverse correlation when the temperature was further increased. This suggests the release of molecular species unrelated to hydrogen. Following the process of elimination, the only possibility remaining is helium-3.
[0072] Using two fundamentally different techniques—nuclear reaction analysis (NRA) using a deuteron beam and thermal desorption spectroscopy (TDS)—we were able to detect helium-3 in CNZ oxide after a hydrogen exothermic reaction. Helium-3 is an isotope that is extremely rare in the environment, and it is likely that helium-3 was produced as a product of a nuclear fusion reaction within the CNZ oxide. The CNZ oxide analyzed was obtained through a heat generation experiment in a hydrogen atmosphere. Therefore, it is believed that helium-3 was produced from hydrogen. This indicates that four hydrogen atoms condensed into a tetrahedrally symmetrical condensation within the CNZ oxide, which is believed to verify the accuracy of the aforementioned 4H / TSC model. The TSC model posits that the ordering and constraints of particles (deuterons, protons, and electrons) in proton-containing condensed matter result in deuteron (proton) cluster fusion reactions. The 4H / TSC model predicts that helium-3 is produced as one of the final major products of a four-proton fusion reaction. Helium-3 is an unstable nucleus (intermediate compound) produced by interactions after tetrahedral symmetric condensation. * It is one of the direct reaction products when 3He-4 is split, and the reaction generates heat. From the above experiments, it is clear that the relationship between the amount of heat generated and the amount of helium-3 produced is consistent with the 4H / TSC model.
[0073] Tokamak-type fusion and inertial fusion using high-intensity lasers attempt to cause a two-body nuclear reaction between deuteron d and triton t. This involves forcing positively charged atomic nuclei into close proximity by using an external magnetic field created by a huge superconducting magnet or implosion using a large laser. In a device the size of the sun, nuclear fusion would proceed as a natural process under the influence of gravity, but these gigantic devices attempt to use powerful power to cause the reaction. In contrast, the 4H / TSC model describes a process in which four protons p and four electrons e -It starts from the nucleus of hydrogen, the most abundant isotope in the universe. It is, needless to say, a stable isotope. Condensation proceeds spontaneously from a highly symmetric arrangement of protons and electrons. High spatial symmetry and harmony are the starting point, not collisions at extremely high temperatures. Furthermore, a series of spontaneous processes occur: Bose-Einstein condensation of electrons, the conversion of protons to neutrons through weak interactions, the production of the unstable nucleus Li-4 through strong interactions, and its fission. As a result, this reaction is unlikely to generate neutrons or radioactive materials. Furthermore, because it is unlikely to produce neutron-rich nuclei, residual radioactivity is low. If the Ni and Cu inside the CNZ oxide act as the cradle for the reaction, the reaction will not proceed above the melting point of the CNZ oxide.
[0074] (Nuclear fusion efficiency in the nuclear reaction generator) FIG. 10 is an explanatory diagram of the nuclear reaction efficiency in the nuclear reaction generator 1. In FIG. 10, the inlet temperature of the heat transfer medium (refrigerant) 7 flowing through the cooling section 2 is T in , the outlet temperature is T out , the flow rate of the heat medium (refrigerant) 7 is F, the specific heat of the heat medium (refrigerant) 7 is c, and the dissipated heat energy L dis The amount of energy injected into the heating element 4 by the heater 5 is P ex (T c ), the amount of energy generated by the nuclear reaction occurring inside the heating element 4 is P fu (T c The operation of a cold fusion reactor is controlled by the amount of energy input from the outside, that is, the amount of energy P ex (T c ) is minimized from the viewpoint of thermal energy utilization efficiency. At that time, the nuclear fusion efficiency defined by the following formula 3 is maximized. Furthermore, the following formula 4 is an inequality that holds when the nuclear reaction has been in a steady state for some time. In formula 4, the denominator is the total amount of energy injected and the amount of energy produced by the nuclear reaction, that is, the total amount of energy given to or produced within the nuclear reaction device, and the numerator is the amount of energy P produced by the nuclear reaction. fu (T c ) was selected.
[0075] Fusion efficiency (ηfu ) = P fu (T c ) / {(T out -T in ) cF+L dis} = P fu (T c ) / {P ex (T c ) + P fu (T c )} ...(Formula 3)
[0076] 0.167< η fu ≦1.0 ... (Formula 4)
[0077] If heater 5 is used only as a starter to initiate the nuclear reaction, and the nuclear reaction continues in the steady state with heater 5 turned off (which is the ideal state), then η fu On the other hand, at present, even in the steady state, energy injection by the heater is necessary, and η fu = 0.2 or so has been achieved.
[0078] Figure 11 shows a graph of the nuclear reaction efficiency obtained by changing the number of times the samples were re-fired (fired in air). Samples 1 to 5 are all sample lots in which the heating element is CNZ oxide, and the number of times the samples were re-fired is 0 for sample 1, 1 for sample 2, 2 for sample 3, 3 for sample 4, and 4 for sample 5. As shown in Figure 11, at 160 W, samples 1, 3, and 5 had η fu It can be seen that a conversion efficiency of 0.167 is achieved. In a real device, it is necessary to estimate the conversion efficiency of the fusion reaction by taking into account the effect of energy dissipation. Therefore, the effective fusion conversion efficiency (ε eff ) parameter is introduced. The dissipated heat energy term is expressed by the following equation 5. Then, assuming that the energy efficiency is 100%, that is, L dis = 0, the effective nuclear reaction conversion efficiency (ε eff ) is defined as the following formula 6.
[0079] P ex (T c ) + P fu (T c ) = (T out -T in ) cF+Ldis ...(Formula 5)
[0080] Effective nuclear reaction conversion efficiency (ε eff ) = (T out -T in ) cF / P fu (T c ) ... (Formula 6)
[0081] L dis = 0, and substituting Equation 6 into Equation 5, ε eff =P ex (T c ) / P fu (T c ) + 1, and the amount of energy injected is P ex (T c ) can be made zero, then ε eff = 1. Similarly, L dis If we set ε = 0, eff = (T out -T in ) cF / P fu (T c ) = [{P ex (T c ) + P fu (T c )}-L dis ] / P fu (T c ) = {P ex (T c ) + P fu (T c )} / P fu (T c ) where η fu =P fu (T c ) / {P ex (T c ) + P fu (T c )) to obtain ε eff = 1 / η fu Therefore, η fu When ε = 0.167, eff = 6. Therefore, for samples 1, 3, and 5, η fu >0.167, and ε eff <6 has been achieved.
[0082] Figure 12 shows cross-sectional views of the cylindrical vessel 3 in the nuclear reaction generator 1, where (1) shows a cross-sectional view of the vessel 3 in the short direction and (2) shows a cross-sectional view of the vessel 3 in the long direction. As shown in Figure 12 (1), the thickness of the heating element 4 in the vessel 3 is limited so that it is positioned within a certain distance D from the contact point with the heater 5. This allows the entire heating element 4 to be heated spatially uniformly. When heated in a vacuum state without hydrogen gas 8, the surface temperature (T H ) and the surface temperature on the hydrogen gas 8 side (T S ) is designed so that the temperature difference between the heater and the reactor is 80° C. or less. That is, in the nuclear reaction generating device, the heating element is arranged within a predetermined distance from the contact part with the heater, and the heating element has a predetermined thickness.
[0083] For example, if we assume that the thermal conductivity of the heating element is the same as the thermal conductivity of zirconia (3 [W / mK]), which is the majority of the CNZ oxide that is the heating element, then in a one-dimensional flat plate system, the thickness is 3 mm and the area is 5 × 5 cm. 2 If the heater input is 200 [W], ΔT = (3 / 1000) [m] × 200 [W] / (3 [W / mK] × 0.0025 [m 2 ]), and ΔT = 80 [K]. The temperature difference between the heater side and the refrigerant side can be set to 80°C. The thermal conductivity of zirconia does not change significantly within the range from room temperature to around 600°C.
[0084] Figure 13 is a graph showing the temperature difference between the sample temperature and the calibration zirconia beads. Both Sample 6 and Sample 7 were from a sample lot with a CNZ oxide heating element and a particle size of less than 75 μm. However, Sample 6 had never been refired, while Sample 7 had been refired once. As shown in Figure 13, when the sample temperature exceeded 350°C, the temperature difference ΔT with the calibration zirconia beads reached +20°C, indicating significant heat generation. Furthermore, as the sample temperature approached 600°C, the temperature increase slowed down, indicating that saturation was approaching.
[0085] Figure 14 shows the correlation between the pressure of hydrogen gas 8 and excess heat (ΔT). Sample 8 is a sample lot in which the heating element is CNZ oxide, the particle size of the sample is less than 75 μm, and the number of re-fires was one. In Figure 14, the reactor pressure on the horizontal axis is absolute pressure, and the vertical axis represents the temperature difference with the calibration zirconia beads. The pressure parameter of the hydrogen gas in the vessel is determined by balancing the ease of nuclear reaction due to the potential availability of CNZ oxide and the heat transfer effect due to the thermal conductivity of the hydrogen gas. The pressure at which heat generation was confirmed (1 atmosphere: approximately 0.1 MPa) is set as the lower limit, and 10 atmospheres (approximately 1 MPa) or less is set as the limit at which handling as high-pressure gas is not required. Therefore, the supply of hydrogen gas 8 can be controlled so that the pressure of the hydrogen gas in the vessel 3 is between 0.1 MPa and 1 MPa, thereby increasing the efficiency of the excess heat reaction.
[0086] FIG. 15 shows a schematic diagram of another embodiment of a nuclear reaction generator. As shown in FIG. 15, the nuclear reaction generator 1a comprises a cooling unit 2, a container 3a, a heating element 4a, a heater 5, a thermocouple 6a, and a heater control unit 12a. The cooling unit 2 contains a heat transfer medium 7 and is provided with an inlet 21 and an outlet 22 for the heat transfer medium 7. A container 3a is provided inside the cooling unit 2, and a heating element 4a and a heater 5 are provided within the container 3a and are sealed by the container 3a. The heating element 4a induces interaction between hydrogen gas atoms to generate a nuclear reaction and is made of a material containing an occlusion substance capable of occluding hydrogen. Unlike the nuclear reaction generator 1 of Example 1, the nuclear reaction generator 1a does not supply hydrogen gas 8 from a hydrogen gas tank 11, but instead uses hydrogen gas (not shown) previously occluded in the heating element 4a to generate a nuclear reaction. The heater 5 heats the heating element 4a to a predetermined temperature or higher and maintains the temperature. In addition, a thermocouple 6a (sample) is introduced inside the heating element 4a, and the heater control unit 12a controls the heater 5 based on the temperature data obtained from the thermocouple 6a so that at least a portion of the heating element 4a is within a predetermined temperature range.
[0087] FIG. 16 is a schematic diagram of another embodiment of a nuclear reaction generator. As shown in FIG. 16, the nuclear reaction generator 1b of Example 4 is composed of a cooling unit 2, a container 3b, a heating element 4b, a heater 5a, a thermocouple 6a, and a heater control unit 12a. The cooling unit 2 contains a heat transfer medium 7 and is provided with an inlet 21 and an outlet 22 for the heat transfer medium 7. A container 3b is provided inside the cooling unit 2. A heating element 4b is provided within the container 3b and is sealed by the container 3b. A heater 5a is spirally wrapped around the container 3b. The heating element 4b induces interaction between hydrogen gas atoms to generate a nuclear reaction and is made of a material containing an occlusion substance capable of occluding protons. Similar to the nuclear reaction generator 1a of Example 3 described above, the nuclear reaction generator 1b is configured to generate a nuclear reaction using hydrogen gas (not shown) previously occluded in the heating element 4b. The heater 5a heats the heating element 4b to a predetermined temperature or higher and maintains the temperature. In addition, a thermocouple 6a (sample) is introduced inside the heating element 4b, and the heater control unit 12a controls the heater 5a based on the temperature data obtained from the thermocouple 6a so that at least a portion of the heating element 4b is within a predetermined temperature range.
[0088] Figure 17 shows a schematic diagram of the configuration of another embodiment of a nuclear reaction generator. As shown in Figure 17, a nuclear reaction generator 1c has a cooling section 2a arranged in a spiral shape inside a container 3. This structure improves the heat exchange efficiency between the heating element 4 and the heat medium 7. The rest of the configuration is the same as that of the nuclear reaction generator 1 of Example 1 described above.
[0089] 18 and 19 are schematic diagrams illustrating other embodiments of the structure of the vessel 3 of a nuclear reaction generator. The vessel shown in FIG. 18 (1) has a central heater 5, a hollow cylindrical heating element 4 positioned around the heater 5, and the vessel 3 sealing the outer periphery of the heating element 4, and a passage through which hydrogen gas 8 flows from the heating element 4. The passage for hydrogen gas 8 is formed, for example, with a stainless steel mesh 40, and is configured so that the hydrogen gas 8 and the heating element 4 come into contact. The heating element 4 is controlled by the internal heater 5 to maintain a spatially constant temperature, and the thermal energy generated by the heating element 4 is efficiently released to the outside via the vessel 3. Note that the hydrogen gas 8 filled in the vessel 3 may flow through a pipe connected to the vessel 3, circulating between the vessel 3 and the pipe. Furthermore, by enabling heat exchange with the outside in part of the pipe, a thermal cycle using the hydrogen gas 8 as a heat medium (refrigerant) can be realized. In this case, the temperature inside the vessel 3 may be controlled by controlling the flow rate of the hydrogen gas 8.
[0090] The container shown in Figure 18(2) has a structure consisting of a central heater 5, a hollow cylindrical heating element 4 positioned around the heater 5, and a container 3 that seals the outer periphery of the heating element 4, and a passage through which hydrogen gas 8 from the heating element 4 flows. Also, unlike the container shown in Figure 18(1), a cooling unit 2 is inserted into the container 3, and a heat medium 7 circulates inside the cooling unit 2. This allows the thermal energy generated by the heating element 4 to be efficiently released to the outside via the cooling unit 2. The rest of the configuration is the same as the container shown in Figure 18(1).
[0091] The container shown in FIG. 19(1) differs from the container shown in FIG. 18(1) in that a total of five heaters 5 are provided in the center and around the periphery. By distributing multiple heaters 5 with smaller shapes, the heating element 4 can be heated efficiently. The container shown in FIG. 19(2) has more cooling parts 2 inserted therethrough than the container shown in FIG. 18(2). The cooling parts 2 shown in FIG. 19(2) may function individually or may be connected at their ends. In this way, by providing a large number of cooling parts 2 with smaller diameters, the number of contact points with the heating element 4 can be increased, improving heat exchange efficiency.
[0092] In the above embodiment, a single heating element is installed in the vessel, but the present invention is not limited to this configuration. For example, multiple heating elements, such as two heating elements, may be installed in one vessel. By using such a configuration, a nuclear reaction generator that generates a larger amount of heat can be obtained.
[0093] Inside the CNZ alloy oxide, He-3 is generated as one of the products of the nuclear fusion reaction. As mentioned above, the base material zirconium oxide (ZrO 2 The process by which He-3 is produced by absorbing hydrogen into a CNZ alloy oxide, in which a Ni-Cu alloy is dispersed, can only be explained by a nuclear fusion reaction. By subjecting the CNZ alloy to specific processing to absorb hydrogen and then sintering it, He-3 remains stable within the alloy. He, an inert rare gas with a small atomic size, does not easily escape from the solid into a gas. While He readily migrates between the lattices of a perfect crystal, He does not easily escape when captured by lattice defects such as vacancies, and perfect crystals do not exist. Below, a manufacturing flow for He-3 according to one embodiment of the present invention is shown with reference to FIG. 20, and an example of a manufacturing process for He-3 is described with reference to FIG. 21.
[0094] First, a CNZ alloy, which is an amorphous alloy composed of Cu, Ni, and Zr, is prepared (step S01). The CNZ alloy is prepared based on a preset composition ratio. Next, the CNZ alloy is fired in the atmosphere at 400 to 500°C (step S02). The amorphous alloy is heated to, for example, 450°C in a crucible 61 to be oxidized. The firing time depends on the amount of alloy, but is typically 20 to 100 hours, for example, 60 hours. Note that this oxidation converts Zr to ZrO. 2It is believed that the oxidation causes some Cu to be oxidized to produce copper oxide, but that Ni is hardly oxidized. The oxidized CNZ alloy (referred to as CNZ alloy oxide) is pulverized to obtain fine alloy oxide (step S03). The pulverization can be carried out automatically, for example, in a mortar. The average particle size of the pulverized alloy oxide is 1 mm or less, preferably 0.5 mm or less, and the volume average particle size is preferably in the range of 0.05 to 0.3 mm.
[0095] Then, hydrogen is absorbed into the fine alloy oxide obtained in step 3 (step S04). To absorb hydrogen into the fine alloy oxide, hydrogen gas (protium) is supplied to the CNZ alloy oxide in the sample container 61 placed in a vacuum reactor (sealed container 62). Hydrogen absorption is performed for several hours or more at approximately 4 atmospheres and 400-500°C. For example, hydrogen is absorbed into the CNZ alloy oxide at 4 atmospheres and 450°C for 5 hours. The pulverized CNZ alloy oxide is then calcined in air at 400-500°C (step 5). This is performed for 100-250 hours. Calcination in air may be repeated. He-3 is generated within the alloy oxide that has absorbed hydrogen, and the alloy oxide stably retains the He-3 inside.
[0096] Thereafter, the alloy oxide is isochronously heated in a nitrogen or argon atmosphere to 900°C or higher (step S06), whereby the He-3 held in the alloy oxide can be extracted (step S07). As described above, in the thermal release curve (see FIG. 8) of the molecular species detected as a signal with mass number 3 from the CNZ alloy oxide, in the case of the CNZ alloy oxide sample (after the hydrogen exothermic reaction), the signal rises sharply above 900°C, and the signal rises higher than that of the sample dish alone or the CNZ alloy oxide before the hydrogen exothermic reaction. The signal of release in the temperature range above 900°C is H 2 and H 3 + There is little correlation between these two, which is the signal for the emission of He-3.
[0097] Furthermore, since the boiling point of He is low at -269°C at 1 atmosphere (-253°C for hydrogen and -195.8°C for nitrogen), it can be identified that He remains in a gaseous state until the temperature of the gas extracted from the alloy oxide is lowered to -268°C, and that He-3 remains in a gaseous state until the end because it has a lower boiling point than normal He. Additionally, gases containing He-3 released from inside the alloy oxide can be separated using known methods.
[0098] In the above Example 1, the method for producing He-3 was explained using CNZ alloy oxide as an example. However, the alloy as the starting material is not necessarily a CNZ alloy (Cu—Ni / ZrO 2 system), but PNZ alloy (Pd-Ni / ZrO 2 system), CNS alloy (Cu-Ni / SiO 2 ), PNS alloy (Pd-Ni / SiO 2 In this case, both systems generate heat through nuclear fusion reactions, and He-3 can be produced without generating radioactive materials.
[0099] The present invention is useful for nuclear reaction generators that involve cold fusion. The energy of the nuclear reaction of the present invention is decarbonized and deradioactive, enabling the ultimate efficient use of hydrogen fuel. It is also useful for hot water heaters in private homes, public baths, and other facilities that attract customers. By increasing the size of the device, it can be applied to power generation facilities and is expected to become an energy source that can be used in the ocean, deep sea, and space.
[0100] Furthermore, the present invention is useful as a method for producing He-3, and the produced He-3 can be used for neutron measurement, dilution refrigeration using He-3 and He-4, and as fuel for nuclear fusion reactors.
[0101] REFERENCE SIGNS LIST 1, 1a to 1c nuclear reaction generator 2, 2a cooling unit 3, 3a, 3b container 4, 4a, 4b heating element 5, 5a heater 6a, 6b thermocouple 7 heat transfer medium (refrigerant) 8 hydrogen gas 11 hydrogen gas tank 12, 12a heater control unit 13a, 13b pressure gauge 14 valve 15 piping 21, 21a intake port 22, 22a exhaust port 40 stainless steel mesh 50 CNZ alloy oxide 52, 53 hydrogen-absorbing CNZ alloy oxide 61 sample container (crucible) 62 airtight container 63 gas storage container 100 nuclear reaction test device 101 glass tube 102 vacuum
Claims
1. A nuclear reaction generating device comprising: a heating element that induces interactions between hydrogen atoms to generate a nuclear reaction; a container that seals the heating element and hydrogen; and a heater that heats the heating element to a temperature above the reaction initiation temperature at which excess heat is generated, wherein the heating element induces interactions between hydrogen atoms and generates He-3 (helium 3) inside.
2. A nuclear reaction generating device as described in claim 1, further comprising: a cooling section through which a heat transfer medium (refrigerant) flows to extract heat from the heat generating element; and a heater control section that controls the heater so that the temperature of the heat generating element decreases due to heat dissipation from the heat generating element and heat absorption by the heat transfer medium, and does not fall below the reaction initiation temperature but remains within a predetermined temperature range, and so that the spatial distribution of the temperature of the heat generating element remains within a predetermined range.
3. A nuclear reaction generating device as set forth in claim 1 or 2, further comprising at least one of a supply unit for supplying hydrogen to the inside of the container, or a heat-retaining unit for preventing heat dissipation from the heating element.
4. A nuclear reaction generating device as claimed in any one of claims 1 to 3, wherein when a cross section of the container is viewed, there is a portion in which the heating element, the hydrogen, and the container are arranged in this order, or when a cross section of the container is viewed, there is a portion in which the heater, the heating element, and the container are arranged in this order.
5. A nuclear reaction generating device according to any one of claims 1 to 4, wherein the reaction initiation temperature is 300 to 350°C.
6. A nuclear reaction generating device according to any one of claims 1 to 5, further comprising a pressure control unit that controls the pressure inside the container, thereby controlling the degree of nuclear reaction occurring in the heating element and controlling the pressure inside the container to within the range of 0.1 to 1 MPa.
7. A nuclear reaction generating device as set forth in any one of claims 1 to 6, wherein the heating element contains an occlusion material capable of occluding protons, and the surface temperature of the container is 150°C or higher and 280°C or lower.
8. A nuclear reaction generator according to any one of claims 1 to 7, wherein at least one of the following formulas 1 and 2 is established: (Formula 1) Energy produced by the nuclear reaction generator > Nuclear fusion energy released when He-3 (helium 3) is produced from hydrogen (Formula 1); (Formula 2) 1 / 100 < Nuclear fusion energy released when He-3 (helium 3) is produced from hydrogen / Energy produced by the nuclear reaction generator < 1 / 2 (Formula 2).
9. A method of generating a nuclear reaction by sealing a heating element and hydrogen in a container, inducing an interaction between hydrogen atoms using the heating element to generate a nuclear reaction and producing He-3 (helium 3) inside.
10. The method for generating a nuclear reaction according to claim 9, wherein at least one of the following formulas 3 and 4 is established: (Formula 3) Energy produced by the method for generating a nuclear reaction > Nuclear fusion energy released when He-3 (helium 3) is produced from protons... (Formula 3); (Formula 4) 1 / 100 < Nuclear fusion energy released when He-3 (helium 3) is produced from protons / Energy produced by the method for generating a nuclear reaction < 1 / 2... (Formula 4).
11. A method for producing He-3, comprising calcining an amorphous alloy consisting of Cu, Ni, and Zr at 400-500°C and pulverizing it, further calcining the alloy oxide that has absorbed hydrogen at 400-500°C, and heating the calcined alloy compound that has absorbed hydrogen to 900°C or higher, thereby extracting the He-3 held in the alloy oxide.
12. The method for producing He-3 according to claim 11, wherein the alloy oxide is heated to 1400°C or higher in a nitrogen or argon atmosphere, and the He-3 is extracted.
13. A method for producing He-3 according to claim 11 or 12, characterized in that the He-3 is released into the ambient gas and then concentrated or separated and purified.
14. A method for producing He-3 according to any one of claims 11 to 13, characterized in that the composition ratio of Cu:Ni:Zr in the amorphous alloy is 1:5-12:10-24.
15. A method for producing He-3 according to any one of claims 11 to 14, characterized in that the He-3 is produced inside the alloy oxide as one of the products of a nuclear fusion reaction.
16. A method for producing He-3, comprising calcining an amorphous alloy consisting of Pd, Ni, and Zr at 400-500°C and pulverizing it, further calcining the alloy oxide that has absorbed hydrogen at 400-500°C, and heating the calcined alloy compound that has absorbed hydrogen to 900°C or higher, thereby extracting the He-3 held in the alloy oxide.
17. The method for producing He-3 according to claim 11 or 16, characterized in that Zr in the composition of the amorphous alloy is replaced with Si.
18. A hydrogen storage alloy oxide, which is an alloy oxide retaining He-3, used in the method for producing He-3 according to any one of claims 11 to 17.
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