WO2019138452A1 - Charged particle beam collision-type nuclear fusion reactor - Google Patents

Abstract

[Problem] With nuclear fusion reactors of a plasma system, it is difficult to separate generated particles; there is a risk of tritium leaking; and nuclear fusion has yet to be reached. Charged particle beam collision-type nuclear fusion reactors are able to generate nuclear fusion but have been regarded as having low acceleration efficiency of particle accelerators, as well as a low collision rate, making it impossible to reach break-even. [Solution] The present invention adopts a configuration of using a particle accelerator with high acceleration efficiency and circulating unreacted fuel particles, thus increasing efficiency. Devised are: a charged particle beam collision-type nuclear fusion reactor of a linked type (50c) for separating, in a charged particle state, tritium and helium 3 having been generated in a D-D reactor, and immediately annihilating the tritium in a D-T reactor, to obtain a massive amount of energy; and that of a simple type (50s) that does not involve radioactive material undergoing a D-3He reaction. Also devised are charged particle beam collision-type nuclear fusion reactors of a tritium multiplication type and a breeding type (50t, 50T) that irradiate lithium or the like with neutrons to breed more tritium and multiply output.

Description

Charged particle beam collision type fusion reactor

In the present invention, a fusion fuel available on the ground is collided as a charged particle beam to cause DD reaction and DT reaction, and neutrons (n) and tritium (T) generated by nuclear fusion are immediately generated. The present invention relates to a nuclear fusion reactor which is annihilated, produces helium 3 ( ³ He), and does not involve radioactive materials utilizing D ³ He reaction.

表１　核融合質量欠損計算表
　表１は、核融合に使用する２種類の粒子の合計質量を表形式の計算表にしたもので、矢印で示す核融合反応前の２つの粒子の合計質量と、核融合反応後の２つの粒子の合計質量、並びに、矢印の近傍に示す差分の質量（指数部を省略しているが、１０^－２７ｋｇである。）を示している。
　質量減少分（質量欠損）は、核融合生成粒子の運動エネルギー（Ｋ）になることを表している。
　減少分の質量に、ｃ^２を掛けるとエネルギー（Ｊ）の単位に、さらに６．２４×１０^１８を掛けると電子ボルト（ｅＶ）の単位に変換できる。 The basic types of fusion reactions and reaction formulas are as follows.
D-D reaction D + D → T + p 4.03 MeV
D + D → ³ He + n 3.27 MeV
DT reaction D + T → ⁴ He + n 17.59 MeV
D- ³ He reaction D + ³ He → ⁴ He + p 18.45 MeV
³ He- ³ He reaction ³ He + ³ He → ⁴ He + 2p 12.86 MeV

Table 1 Fusion mass defect calculation table Table 1 shows the total mass of two types of particles used for nuclear fusion in the form of a tabular calculation table, and the total mass of the two particles before the fusion reaction shown by the arrows. The total mass of the two particles after the fusion reaction, and the mass of the difference shown in the vicinity of the arrow (the index part is omitted but is 10 ^-27 kg).
The mass loss (mass defect) represents the kinetic energy (K) of the fusion product particle.
The mass of the decrease can be multiplied by c ² to convert it to the unit of energy (J), and further multiplied by 6.24 × 10 ¹⁸ to convert it to the unit of electron volt (eV).

The physical properties of the substance used for nuclear fusion in the present application are as follows.
D: Deuterium-deuterium 0.015% contained in natural water, and sufficient quantity as fusion fuel is made available.
The energy required for the production of deuterium is mostly the energy required for the purification of "heavy water" and requires 57 MWh (megawatt hour) of energy to produce 1 kg of heavy water.
T: Tritium, tritium Tritium (T) is regarded as the least toxic radioactive substance that beta-disintegrates with a half-life of 12.3 years, but the risk of internal exposure is pointed out.
³ He: Helium 3
Helium 3 ( ³ He) is a safe fusion fuel that does not generate radiation.
⁴ He: Helium 4
Helium 4 ( ⁴ He) is a stable and safe substance, the nucleus of which is called alpha particle (α) and, together with the proton (p, hydrogen nucleus), is the final fusion product.

Here are the major fusion reactor types that are being studied around the world.
<What uses plasma>
Main nuclear fusion systems that use plasma include magnetic confinement type, inertial confinement type, electrostatic confinement type, etc., using charged particle accelerators to implant charged particles etc. into plasma to heat plasma, nuclear fusion It includes things that try to ignite.

Magnetic confinement fusion reactor (Tokamak type, helical type, magnetic mirror type, etc.)
A magnetically confined nuclear fusion reactor is intended to confine plasma with strong magnetic field lines, and to inject microwaves or charged particle beams to heat the plasma until the temperature at which nuclear fusion occurs.
The Fusion Science Research Institute has succeeded in raising the ion temperature to 120 million degrees C, which is necessary for power generation, in an experiment using a device called "helical type,""by the middle of this century I want to achieve it. "
The International Fusion Research Reactor (ITER) is planning to produce 500 MW of heat output in 2035.
There is no mistake that nuclear fusion will occur if the temperature of plasma ions is raised, but although we have been researching for over 50 years, the information that "a nuclear fusion phenomenon was observed" exists. Not.
Even if nuclear fusion occurs, it is pointed out that the danger of using plasma containing a large amount of tritium (T) in the reactor.

Inertial confinement type fusion reactor (laser type, heavy ion inertial fusion, etc.)
Inertial confinement fusion reactors place fusion fuel pellets of several millimeters in diameter at the center of the reactor and compress them by irradiating them with a powerful laser and charged particle beam from all directions to transform the fusion fuel into a high density plasma The idea is to generate nuclear fusion.
Problems such as inability to uniformly implosion are raised, and it is said that "neutron has been observed." However, helium 3 ( ³ He) of fusion product particles is not detected, and the fusion phenomenon is confirmed It has not been.
Even if fusion occurs, not all fusion fuel of small fuel pellets will react, so it is necessary to purify tritium (T) etc. from the fusion product particles.

Electrostatic confinement type fusion reactor (Fuser type, Farnsworth type etc)
The electrostatic confinement fusion reactor is a system called a fuser type, etc., which applies a voltage to a grid-like electrode provided inside to form a strong electrostatic field, and is considered to be a system where a nuclear fusion phenomenon has been confirmed .
It is put to practical use as a neutron source by nuclear fusion, but the fusion reaction rate (η _f ) is said to be low.

<Muon catalytic fusion>
The “muon catalyzed fusion” is a method of generating fusion reaction by bringing deuterium (D) and tritium (T) nuclei close to each other by giving a large mass negative muon to a DT molecule.
Because it takes 4 GeV to make muons and obtains 17.6 MeV of energy in one DT reaction, break-even can be achieved if one muon achieves 250 fusions or more, but currently 150 times. It is an extent.
Deuterium (D) and tritium (T) are used as DT molecules as fuel, cooled to 5 to 30 K °, and confined in a furnace at 10 atm.
Assuming that breakeven is achieved, nuclear fusion generates high-energy helium 4 ( ⁴ He), which collides with the surrounding fuel gas and raises the temperature of the cryogenically cooled fuel gas. It may not be possible to maintain the initial conditions.

Cold Fusion
Although it has been confirmed that nuclear transformation takes place, no nuclear fusion phenomenon has been observed and no mechanism has been elucidated.
In recent years, research has been advanced by correcting the designation “aggregation system nuclear fusion” and the like.
Even if nuclear fusion can be realized, the reaction is considered to be limited in the reaction because it is a reaction in a solid and the reaction rate is limited.

<Charged particle beam collisional fusion>
This is a system that accelerates and collides charged particles with a particle accelerator (62) used in nuclear research, elementary particle research, etc. to generate nuclear fusion.
As expected, nuclear fusion occurs without fail, but there is a limit to raising the fusion reaction rate (η _f ), and accelerated fuel particles are wasted. (Patent Document 1, 2)
The fusion reaction rate (η _f ) of the particles is low, the acceleration efficiency (η _a ) of the particle accelerator (62) is as low as 5% or less, and the beam current is as low as several pA or less. Low rates (実 施_f ) have been conducted only for good academic research.
Since there is no particle accelerator (62) with good acceleration efficiency (η _a ) that can be used for nuclear fusion for power use, charged particle beam collisional fusion (50) "provides an output energy larger than the input energy It can not be expected. ”(Non-Patent Document 1) was denied, and research has not been conducted.

Patent application No. 2015-00007 Charged particle beam collision type fusion reactor Patent application No. 2016-179051 Charged particle beam asymmetric collision type nuclear fusion Patent No. 4865934 (WO2011 / 136168) Charged particle accelerator and method of accelerating charged particles Patent 2015-207517 Charged particle accelerator Patent application No. 2011-0775452 Metal capillary manufacturing apparatus, metal capillary manufacturing method, metal capillary, and ion beam irradiation apparatus equipped with metal capillary Patent document 4802340 (WO 2006/008840) spherical aberration correction electrostatic lens, input lens, electron spectrometer, photoelectron microscope, and measurement system

"Numerical calculation of fusion plasma" http: // repository. kulib. kyoto-u. ac. jp / dspace / bitstreamkn83392 / 1 / 0832-04.pdf Japan Atomic Energy Research Institute Direct energy conversion jspf 1995_06-516 Plasma Fusion Research Society Dispersed Charged Particle Accelerator Overview http: // www. emcube. co. jp / acceleratorsummary. html JENDL-4.0 general-purpose standard nuclear data library http: // wwwndc. jaea. go. jp / jendl / j40 / J40_J. html Japan Atomic Energy Agency Recommendation 1973 ICRP Publication 21 P94 Figure 19 International Commission on Radiological Protection Serialization course Structure of a fusion reactor well understood Japan Atomic Energy Research Institute Production and chemistry of fusion reactor fuel tritium Japan Atomic Energy Research Institute Cutting-edge research and development of solid tritium breeder materials Plasma Nuclear Fusion Society

<Problems of plasma system>
In any of the nuclear fusion methods using plasma, no nuclear fusion has been observed, and it can not be said that the possibility of realization is high.
For example, even if nuclear fusion generation is successful, there is a problem that nuclear fusion produced charged particles (49c) mix in plasma (fuel particles), and proton (p) which is final fusion produced particles (49f) from plasma And helium 4 ( ⁴ He) can not be separated immediately.
Since it contains tritium (T), which is a fusion produced charged particle (49c) and a fusion fuel, there is always a risk of leakage even when part of the plasma is taken out for separation processing.

The D- ³ He reaction is considered to be a safe fusion reaction, but since deuterium (D) and helium 3 ( ³ He) are mixed, reactions such as DD reaction will be involved Therefore, unfortunately, the plasma method can not be used as safe nuclear fusion.
Fusion of using ^helium-3 only (3 the He) as fusion fuel is available safe ^{3 He-3} the He reaction, D-D, D-T , more difficult fusion reactions, such as ^D-3 the He It is assumed that there is almost no helium 3 ( ³ He) on the ground, so there is no practicality of a powered fusion reactor that uses this reaction alone.

The kinetic energy (K) of fusion-produced charged particles (49c) flying isotropically in all directions repeatedly collides with other particles in the plasma, resulting in disordered thermal energy (Q). Direct power conversion was difficult.
There is also a concept (non-patent document 2) to separate high temperature plasma into electrons and charged particles by electromagnetic force and perform velocity modulation to obtain electric energy (E) by direct power conversion, but there are many stages of complicated processing As the efficiency (η) decreases, there is a risk of leakage of tritium (T).
As to tritium (T), in addition to a method of taking out to the outside and converting it back to a gas and separating by chemical treatment, a method of separating according to the difference of mass to charge ratio (m / z) in the state of charged particles is also considered.
Proton (p) and tritium (T) are considered to be separable, but deuterium (D) and helium 4 ( ⁴ He) have almost the same mass-to-charge ratio (m / z). There is difficulty in separating in the state.

<Problems of charged particle beam collision type fusion>
Since charged particle beam collision-type nuclear fusion is a system in which charged particles are accelerated and collided by two sets of particle accelerators to generate nuclear fusion, nuclear fusion can be generated without fail according to theory, but particles Since the accelerator's acceleration efficiency ( _{a a} ) is as low as 5% or less, and the particle collision rate (η _f ) is low, many particles are wasted, and it was thought that they could not reach break even.

The purpose of the present application is to avoid the influence of neutrons (n) and tritium (T) as much as possible from the fusion reactions that can be used with the substances present on the earth, and how to construct a safe nuclear fusion reactor It is to solve what can be done.

The fusion reaction rate (η _f ) is obtained from the particle density ()) and the fusion reaction cross section (σ).
The fusion reaction cross section (σ) changes depending on the collision velocity of the particles, and the velocity (represented by kinetic energy (K)) appropriate for generating the fusion reaction and the fusion reaction cross section (σ) are It is as follows.
DD reaction; σ = 0.13 to 0.2 barn at 0.5 to 1.4 MeV
DT reaction; σ ≒ 5 barn at 100 keV
D- ³ He reaction; σ ≒ 1 barn at 400 keV
³ He- ³ He reaction; σ 0.01 0.01 barn at 1 MeV
Note that 1 barn is 10 ^-24 cm ² .

<D-D reaction>
When deuterium (D) is collided at 0.5 to 1.4 MeV,
Two reactions of D + D → T + p and ³ He + n occur at a 50% ratio.
You can not choose either response.
Figure 1 is an illustration of a set of DD fusion reactions,
(A) A deuterium (D) consisting of a proton (p) and a neutron (n) collides at an energy of 500 keV for nuclear fusion,
(B) It becomes an unstable helium nucleus containing the energy (U) of the mass deficiency,
(C) Release proton (p) to tritium (T) or
(D) Release neutrons (n) to form helium 3 ( ³ He).

The energy (U) generated by the mass defect is distributed 1: 3 in inverse proportion to the mass of the particle, so 1 MeV for tritium (T), 3 MeV for proton (p), and helium 3 ( ³ He) Are distributed to 0.82 MeV, and 2.45 MeV to neutron (n), and come out in the form of kinetic energy (K) of particles jumping out from each other. (The direction of each flight axis is indeterminate, and the particles fly isotropically in the whole fusion product particle group.)
The kinetic energy (K) possessed by the particles can be converted to electrical energy (E) by temporarily converting it to thermal energy (Q) and further generating power from heat.
Since the flow of charged particles (particles other than neutrons) is equivalent to current, the kinetic energy (K) of the charged particles can be directly converted to electric energy (E) using electromagnetic induction.
Neutrons (n) are dangerous particles, but they can be shielded to prevent them from leaking out of the reactor. (There is a track record in nuclear fission reactors, which can be moderated and absorbed by the neutron moderator (10).)

Next, tritium (T) is a dangerous substance, so how to make it harmless.
In the case of a 200 MW fusion reactor, since it will produce 11 kg or more of tritium (T) a year, it is extremely dangerous if it is accumulated.
It is desirable that the generated tritium (T) be instantaneously separated and recovered, and be eliminated by the DT reaction described below.

<D-T reaction>
When tritium (T) and deuterium (D) collide at 100 keV, the reaction of D + T → ⁴ He + n gives a kinetic energy (K) of 17.59 MeV.
Figure 2 is an illustration of a set of DT fusion reactions,
(A) The collision of tritium (T) and deuterium (D) at a kinetic energy (K) of 0.1 MeV causes nuclear fusion.
(B) It becomes an unstable helium nucleus containing the energy (U) of the mass deficiency,
(C) It emits neutrons (n) and changes to stable helium 4 ( ⁴ He).

The energy (U) generated by the mass defect is distributed 1: 4 in inverse proportion to the mass of the particle, 3.5 MeV in Helium 4 ( ⁴ He) and 14 MeV in Neutron (n) It comes out in the form of kinetic energy (K) of particles that rush out in the direction.
Helium 4 ( ⁴ He) is a charged particle capable of direct power conversion.
If tritium (T) generated in the DD reaction can be eliminated within 1 millisecond, it can be calculated that the instantaneous abundance can be reduced to 1 μg or less.
11,540 / (365 × 24 × 3600 × 1000) = 0.000000366 [g]

<D-3 He reaction>
When helium 3 ( ³ He) and deuterium (D) collide at 400 keV,
The reaction of D + ³ He → ⁴ He + p gives an energy (U) of 18.45 MeV.
Because the fusion product particle contains neither neutron (n) nor tritium (T), it is regarded as a safe fusion reaction.
In the plasma system in which deuterium (D) and tritium (T) are mixed, it is a fusion reaction that can not be used as a safe fusion reaction.

Figure 3 illustrates the D- ³ He fusion reaction, which occurs more easily than the D-D reaction.
(A) collide with energy of 400 keV,
(B) It becomes an unstable lithium nucleus containing energy (U) of mass deficiency,
(C) Release protons (p) to change to stable helium 4 ( ⁴ He).

The energy (U) produced by the mass defect is distributed 1: 4 in inverse proportion to the mass of the particle, 3.7 MeV in Helium 4 ( ⁴ He) and 14.8 MeV in Proton (p), Each comes out in the form of kinetic energy (K) that jumps out in the opposite direction.
Helium 4 ( ⁴ He) and proton (p) are both charged particles capable of direct power conversion, and D- ³ He reaction is a safe nuclear fusion reaction that does not contain radioactive materials, and at the same time direct power conversion. It has the excellent feature that it is possible to construct a lightweight furnace with little heat generation.

First, D-D reaction is performed, then D-T reaction is performed, and tritium (T) is annihilated. By linking nuclear fusion reactions, helium 3 ( ³ He ), Helium 3 ( ³ He) can be used immediately or stored as a safe fusion fuel.
It is calculated that 11 kg or more of helium 3 ( ³ He) can be produced annually with a 200 MW power reactor, and can be used as a fuel for a D- ³ He reactor (simple reactor) that can be used as an engine of a mobile unit.
^{The 3} He- ³ He reaction can also be used as a safe fusion reaction, but since the fusion reaction cross section (σ) is small, it is more practical to use the D- ³ He reaction.

Factors to consider when deciding on a safe fusion reactor strategy are:
-A system capable of using fusion fuel abundantly available on the earth.
-A system in which fusion occurs reliably without wasting fusion fuel.
-Fusion fuel particles and fusion produced charged particles (49c) can be easily separated and not mixed.
-The ability to immediately eliminate tritium (T), which is a dangerous radioactive substance.
-A system capable of directly converting kinetic energy (K) of charged particles into electrical energy (E).
It can be concluded that fusion reactors using plasma do not lead to fusion generation, and because fusion fuel particles and fusion produced particles are mixed, they can not be adopted.

Although charged particle beam collisional nuclear fusion is a method known to ensure nuclear fusion, it is a method that has been used only for research, so whether it can be configured for power use or not To consider.
In the D-D reaction, collision requires 500 keV and kinetic energy (K) of 3.27 MeV and 4.03 MeV can be obtained, so the kinetic energy (K) averages 7.3 times the input kinetic energy (K) However, if the efficiency of the particle accelerator (η _a ) is less than 5%, break even can not be achieved.
Since the acceleration efficiency (η _a ) of the recently developed distributed accelerator (Patent Document 3, Patent Document 4, Non-patent Document 3) is 60%, break even can be achieved.
As a result of the examination, "The charged particle beam collision type fusion which can separate fusion fuel particles and fusion produced charged particles" is selected as the method of fusion reactor.

<Composition of cooperation furnace>
The example which comprises a 200 MW power generating furnace is demonstrated more concretely and demonstrated.
Deuterium (D) is used as the first fuel to generate nuclear fusion by the “tritium annihilation cooperative reactor (50c)” in which the DD reactor and the DT reactor shown in FIG. 4 are combined.
Since neutrons (n) are generated, the reactor is covered with a neutron moderator (10) to shield the neutrons (n), convert their kinetic energy (K) into thermal energy (Q), and generate thermal power Conduct and get electrical energy (E).
On the other hand, direct power conversion is performed by the fusion produced charged particles (49c) to obtain electric energy (E).
Tritium (T) is separated out of the decelerated fusion product charged particles (49c), immediately sent to the DT reactor, and annihilated.
It is also possible to use a combined furnace configured to cause D particles and T particles to alternately or simultaneously collide with one charged particle bunch of deuterium (D).
A method of generating a charged particle beam with a pair of charged particle beam generators (60) and supplying the charged particle beams to a plurality of nuclear fusion reactors (50) is also conceivable.

 表２　「トリチウム消滅連携炉」の所要加速電力及び電気出力 As shown in Table 2, the electrical output of the “tritium annihilation cooperative reactor (50c)” is the kinetic energy (K) of the fusion-produced charged particles (49c, T, p, ³ He) in the DD reaction. If 85% can be directly converted, 48.1 MW of electrical energy (E) can be obtained.
The kinetic energy (K) possessed by the neutron (n) is irradiated to the neutron moderator (10) to convert it into thermal energy (Q), and along with the energy (Q) of the charged particles that are heated and can not be converted to electric power If thermal power generation is performed with a thermal efficiency (η _Q ) of 60%, 22.2 MW of electric energy (E) can be obtained, and a total of 70.3 MW is obtained.

Table 2 Required acceleration power and power of "tritium annihilation cooperative reactor"

In the DT reaction, when 85% of the kinetic energy (K) of the charged particles ( ⁴ He) can be directly converted, an electric energy (E) of 34.9 MW can be obtained. All the energy possessed by the neutron (n) is converted to thermal energy (Q) through the neutron moderator (10), and it is 60% of the energy (Q) of the charged particles which has not been converted to electric power but has turned into heat By performing thermal power generation with thermal efficiency (η _Q ), 102.2 MW of electric energy (E) can be obtained, and a total of 137.1 MW can be obtained.
Kinetic energy required for collision of fuel particles of D-D reaction and D-T reaction (K, considering only high-speed fuel particles, the same applies hereinafter) is 12.8 MW, and acceleration efficiency (η _a ) is 60% , The required electric energy (E) is 21.4 MW, whereas the obtained electric energy (E) is 207.3 MW in total: 82.9 MW for direct power conversion and 124.4 MW for thermal power generation Thus, the “tritium annihilation cooperative reactor (50c)” can obtain 185.9 MW of electric energy (E).

<Composition of simple reactor>
In the D- ³ He reactor shown in FIG. 5, a movable "simple furnace (50s)" can be configured to generate power using deuterium (D) and helium 3 ( ³ He) as fuel.
The D- ³ He reaction does not generate neutrons (n), so there is no need to shield it, so the reactor is lightweight and all fusion product particles are charged particles so direct power conversion is possible and thermal Less occurrence of

表３　「簡易炉」の所要加速電力及び電気出力
　「簡易炉（５０ｓ）」の電気出力は、荷電粒子の持つ運動エネルギー（Ｋ）の８５％を直接電力変換できると１８２．９ＭＷの電気エネルギー（Ｅ）が得られる。直接電力に変換できなかった熱エネルギー（Ｑ）から、６０％の熱効率（η_Ｑ）で熱発電を行うと、１９．４ＭＷの電気エネルギー（Ｅ）を得ることができるので、合計２０２．３ＭＷが得られる。
　Ｄ－^３Ｈｅ反応の衝突に要する運動エネルギー（Ｋ）は、４．７ＭＷであり、加速効率（η_ａ）が６０％である場合、７．８ＭＷの電気エネルギー（Ｅ）を要するので、「簡易炉（５０ｓ）」は、差引１９４．５ＭＷの電気エネルギー（Ｅ）を得ることができる計算であるから、前出の「トリチウム消滅連携炉（５０ｃ）」に匹敵する電気エネルギー（Ｅ）を得ることができる。
 

Table 3 Required acceleration power and electric power of "simple reactor" The electric output of "simple reactor (50s)" can directly convert 85% of the kinetic energy (K) of charged particles to 182.9 MW of electric energy ( E) is obtained. If thermal power is generated with a thermal efficiency (η _Q ) of 60% from thermal energy (Q) that could not be converted directly to electric power, 19.2 MW of electric energy (E) can be obtained, so a total of 202.3 MW is can get.
The kinetic energy (K) required for collision of D- ³ He reaction is 4.7 MW, and when the acceleration efficiency (η _a ) is 60%, 7.8 MW electric energy (E) is required. Since the furnace (50s) is a calculation capable of obtaining a deduction of 194.5 MW of electric energy (E), obtaining an electric energy (E) comparable to the above-mentioned "tritium annihilation cooperative furnace (50c) Can.

<Collision of beam>
The collision method of the charged particle beam will be described.
The nuclear fusion reaction is a particle accelerator (62) which accelerates charged particles generated by ionizing a nuclear fusion fuel gas by a charged particle generator (61) by coulomb force into a bunch of pulsed charged particle beams, charged particles A nuclear fusion reactor (58) using two sets of charged particle beam generators (60) comprising an electron lens (63) for focusing the beam and a deflector (64) for changing the flight direction of the charged particle beam It collides in the center of the to generate a fusion reaction.

A charged particle beam is focused and deflected to a diameter of 1 to 2 μm and a length of 10 cm at the center of the fusion vessel (58), and the speed at which the fusion reaction cross section (σ) determined by the combination of fusion fuels increases The collision energy is about 400 keV in the D- ³ He reaction at a rate that the kinetic energy (K) obtained by nuclear fusion increases with the required kinetic energy (K).
As the collision proceeds, the fusion fuel particles of both charged particle bunches decrease, so the particle collision rate decreases in the latter half of the charged particle bunches.
By increasing the number of low-speed particles on one side and increasing the speed of the other particles, it is possible to prevent a decrease in the collision rate in the latter half of the charged particle bunch and reduce waste of electrical energy (E) required for acceleration.

When the length of the charged particle beam is about 10 cm, the length of the fusion reaction region (52) is also about 10 cm at maximum.
If it is shortened, a large amount of charged particles are ejected in a moment, which places a burden on the electron lens (63), the deflector (64) and the like.
When the length of the charged particle beam is 10 cm or more, the flight width of the fusion produced charged particle (49c) is also increased, which may result in insufficient separation for each nuclide. In the simplified reactor (50 s), there is no need to perform separation for each nuclide, so there is no such limitation.

<Particle accelerator>
Conventional accelerators introduce high-power high-frequency radio waves into the accelerating cavity to form an accelerating electric field, and use high-Q cavities and adding high-frequency waves to cavities without charged particles etc. Therefore, the loss is large and the acceleration efficiency (η _a ) is as low as 5% or less.
The dispersive particle accelerator (62) is a system in which the accelerating voltage is sequentially applied only to the accelerating electrode in the vicinity of the charged particles as the charged particles move, so that the high acceleration efficiency (η _a ) is as high as 60%. is there. (Patent Document 3, 4, Non-patent Document 3)

The charged particles ejected from the particle accelerator (62) perform axial compression by increasing the velocity of particles behind the head.
When using a flat shaped particle accelerator (62), the axially compressed charged particle bunches form charged particle bunches arranged in a transverse row with respect to the direction of travel. When the traveling direction is bent by 90 °, the traveling direction is changed while maintaining the relative positional relationship of the charged particles, so that charged particle bunches aligned in the traveling direction can be formed.

Inside the particle accelerator (62), when a part of the charged particle beam comes in contact with the electrode or the metal part of the accelerator, it may lead to an accident of metal dissolution.
An insulating container such as strong ceramic is provided between the charged particle passage and the electrode to prevent an accident.
Since the scattered charged particles touch the inside of the insulating container to cause charging and affect the trajectory of the charged particle beam, it is necessary to remove the charging.
For this reason, an appropriate conductivity is provided, or after emitting charged particles, acceleration operation is performed without charged particles, and charge removal is performed by a strong electric field.

<Electronic lens>
The electron lens (63) includes an electric field type electron lens (63e) and a magnetic field type electron lens (63m). The electric field type electron lens (63e) is considered to have a large aberration, and mainly the particle accelerator and the ion transfer path Internally, it is incorporated as a structure of the accelerating electrode in order to maintain the beam so as not to disperse the charged particle bunch.
In the charged particle beam collision type fusion reactor (50), since high speed charged particles and low speed charged particle beams are emitted from the same direction, one magnetic field type electron lens (63 m) is used in common and low speed charge After emitting the particle beam (after several microseconds), the magnetic field intensity is changed to match the high speed charged particle beam.

<Capillary>
The capillary (63c) converges charged particles by utilizing the structure of a tapered tube which is made of a strong insulator such as ceramic and which is processed to be thin.
The charged particles incident at a minute angle with respect to the inner wall surface of the capillary (63c) are totally reflected and the charged particles are narrowed according to the inner diameter shape of the tube which becomes gradually narrower, and the electric field electron lens (63e) or the magnetic field electron lens It converges on the principle different from (63 m).
Two or more capillaries (63c) can be arranged side by side in the same direction.

The charged particles, after leaving the tip of the capillary (63c), try to go straight by the inertia of the individual particles, so that the charged particle beam can be finely focused at a fixed distance.
An electrode is provided outside the capillary (63c), and a pulse voltage is applied to prevent charged particles from remaining inside the capillary (63c), and a pulse voltage is applied in a no-load state to perform a removing operation.
The convergence of charged particles by the capillary (63c) is considered to be a guiding effect by the charged particles of the inner surface of the insulator capillary (63c) such as single crystal or polycrystal ceramic, but the small angle by the nuclei forming the metal capillary It has been confirmed that it is possible to focus charged particles also by forward scattering. (Patent Document 5)

<Deflector>
The deflector (64) for changing the direction of the charged particles includes an electric field deflector (64e) and a magnetic field deflector (64m).
Two sets of orthogonal deflectors (64) are used to adjust the flight direction of the charged particle beam by the applied voltage or current.
Since the high-speed charged particle beam and the low-speed charged particle beam are emitted from the same direction, the deflector of the electric field type (64e) is shared and used after emitting the low-speed charged particle beam (a few microseconds Later, change the deflection intensity to match the high speed charged particle beam.
The position where the high speed charged particle and the low speed charged particle are emitted is slightly different, but in order to maintain the fusion reaction rate (η _f ) high, the high speed charge is applied so as to penetrate the low speed charged particle bunch. It is necessary to make the whole particle bunch collide.
Therefore, by changing the voltage while low-speed charged particles are passing through the deflector (64), the inclination of the charged particle bunch relative to the traveling direction is changed as shown in FIG. 6A, and the fusion reaction point (51) , To deflect in the axial direction of the high speed charged particle beam.

In order to cause two (or more) high-speed charged particles to collide with the low-speed charged particles, since the emission position of each particle is different, the correction of the low-speed charged particle bunch inclination alone can Can not collide.
The charged particle bunches are sequentially fired toward the intermediate position between the charged particle emission position and the fusion reaction point (51), and are directed to the fusion reaction point (51) by the deflector (64) provided at the intermediate position. Deflection is performed, and all charged particle bunches follow the same trajectory and collide at the fusion reaction point (51).

<Flight of fusion product particles of DD reaction>
FIG. 6 shows the flight state of the fuel particle of the DD reaction and the fusion product particle.
As shown in FIG. 6A, the low speed charged particle bunch has a diameter of 2 μm, and the high speed charged particle bunch has a diameter of around 1 μm, and both have a length of about 10 cm (the length and thickness are drawn at the same ratio in the figure) Because they can not do so, they are depicted as thick ovals.) The charged particle bunches of Deuterium (D) collide at a relative velocity of 0.5 MeV (6,900 km / s),
As shown in FIG. 6 (b), the fusion reaction proceeds while the fusion product particles (p, n, T, ³ He) are isotropically ejected at the following speed.
Proton (p): 24,000 km / s
Neutron (n): 21,600 km / s
Tritium (T): 8,000 km / s
Helium 3 ( ³ He): 7,200 km / s

As shown in FIG. 6 (c), since the fusion produced particles (p, n, T, ³ He) produced by the fusion go out of the fuel particle beam with a diameter of 2 μm in a very short time, the other fuel It flies without colliding and mixing with particles etc.
As shown by concentric circles in FIG. 6 (d), fusion-produced particles (p, n, T, ³ He) that fly isotropically spread as spherical shells.
Since one of the fuel particles has a downward velocity of 0.5 MeV in the figure, the center of the fusion product particle spreading like a spherical shell travels down the figure at a velocity of 3,450 km / s.
The flight velocity of the fusion product particles (p, n, T, ³ He) traveling upward in the figure decreases by up to 3,450 km / s.
The flight velocity of the fusion generated particle (p, n, T, ³ He) group traveling downward in the figure is added up to 3,450 km / s.

As shown in FIG. 6 (e), the particles with high speed of fusion produced particles are separated into respective charged particle groups in the order of p, n, T and ³ He in order, and reach the peripheral part of the furnace in order. (Since neutron n is not the object of direct power conversion, it is not described in FIG. 6 (e).)
Since the probability that the high-speed particles collide from behind with very low-speed particles is extremely small, fusion-produced charged particles (49c) are sufficiently separated at the periphery of the reactor (more than 5 m from fusion reaction point 51). .

Collision order of high-speed particles
We will consider the order of collisions when D-D reaction and D-T reaction are performed simultaneously.
(1) In the case where high-speed D particles and high-speed T particles collide at the same time or high-speed D particles first, high-speed D particles (500 keV) and T particles (100 keV) before collision with low-speed D particles Collides at a relative velocity of 400 keV, and the fusion reaction cross section (σ) of the DT reaction is 0.8 barns, so up to about 30% of D particles disappear.
As the T particles are reduced, the D-T response of the next cycle is also reduced and the power is reduced by up to about 30%.
(2) When colliding one of high-speed particles from different directions The collision form of the particles is more ideal, but two ion recovery paths (68c) of unreacted fuel particles (49n) are provided. Need to complicate the furnace configuration and the electron lens 63 is exposed to unreacted fuel particles 49n.
(3) In order to avoid high-speed particle collision, the high-speed T particle is made to collide before the high-speed D particle.
Since the D-T reaction partially reduces the density of low-speed D particles, the fusion reaction rate (η _f ) when high-speed D particles collide is fluctuated, but the number of low-speed D particles is If it is large enough, the variation is small.
In addition, since high-speed unreacted fuel particles (49n, D) are circulated again as high-speed fuel particles, they work to suppress output fluctuation.
From the above, the collision order adopts (3).

FIG. 6 (f) shows the flight of the fusion product charged particle (49c) when the DT reaction is generated just before the DD reaction (60 ns before the beginning of the DD reaction). ing.
When DT reaction is added, helium 4 ( ⁴ He, 3.52 MeV, 13,000 km / s) is added to the fusion product charged particle (49c), and it flies by crossing with p particle of DD reaction , The probability of colliding with each other is low.
By direction, the difference in the flight velocity due to the asymmetric collision is included, but in the peripheral part of the reactor (more than 5 m from the fusion reaction point 51), the p particles and ⁴ He particles are sufficiently with other particles. It is separated.
Although T particles and ³ He particles can be separated, the difference in the flight velocity according to the flight direction (indicated by arrows ↓, →→, ↑ in the figure) caused by the asymmetric collision is large, as shown in FIG. As shown in f), when particles in a certain directional range (for example, in the range of 30 °) are collected, mixing of T particles and ³ He particles occurs.
By setting the fusion reaction point (51) 10 to 50 cm above the center (53) of the reactor, the influence of asymmetry can be somewhat reduced.

<Fusion rate of D- ³ He reaction>
The fusion reaction rate (η _f ) of the "D- ³ He" reaction is examined first.
In simple furnace (50s), availability and easy deuterium (D) and low-speed beam, used helium-3 to obtain is difficult (3 ^{the He)} as a high speed beam.
The reaction cross section (σ) of the D- ³ He reaction is about 1 barns (10 ^-24 cm ² ).
When constructing a 200 MW power reactor, it is necessary that 7.28 × 10 ¹⁹ particles be fused each second.
Suppose you make 1000 collisions per second,
A high speed charged helium 3 ( ³ He) charged particle bunch with a length of 10 cm and a diameter of 1 μm,
When impacting into a 10 cm long, 2 μm diameter, 8-fold particle velocity slow deuterium (D) charged particle bunch, the collision error (δ) is acceptable up to ± 0.5 μm, and a slow deuterium (D) The particle density ()) of
ρ = 7.28 × 10 ¹⁹ × 8 / (f × π × (1 × 10 ⁻⁴ ) ² × 10)
1.8 1.85 × 10 ²⁴ [cm ³ ]
It is. However, the particle density (ρ) of the low speed charged particle bunch is 1⁄2 because the shape of the charged particle bunch is not an ideal cylindrical shape, and the low speed particles disappear due to collision and sequentially decrease. As
ρ ≒ 0.927 × 10 ²⁴ [cm ³ ]
I assume.

The mean free path (λe) at which 1 / e particles collide is 1 × 10 ^-24 cm ² for the fusion reaction cross section (σ),
λe = 1 / (ρ · σ)
1.0 1.08 cm
When colliding with a cylinder with a diameter of 1 μm and a length of 10 cm,
(1-1 / e) ^{10 / 1.08} = 1.42 × 10 ^-2
Therefore, helium 3 ( ³ He), which is a high-speed fuel particle, almost disappears.

On the other hand, 87% or more of the low-speed fuel particles of deuterium (D) become unreacted fuel particles (49n). Therefore, by recycling and using the unreacted fuel particles (49n), the utilization rate can be increased. improves.
Since the velocity is 310 km / s when low-speed fuel particles (D) are circulated at 1 keV, it is necessary to construct a fuel particle circuit (69) with a length of approximately 300 m when circulating at 1 millisecond. is there. (It is possible to shorten the length of the fuel particle circuit (69) by reducing the particle velocity.)
Since the high-speed helium 3 ( ³ He) unreacted fuel particles (49n) have no safety problems and are trace amounts, they are returned to the gas by the ion neutralizer (70) together with the scattering particles (49s), Recover to gas cylinder (79) etc.

表４　核融合反応率計算表 Fusion reaction rate
Table 4 is a calculation table of the fusion reaction rate (η _f ) of the “D- ³ He” reaction, the “D-D” reaction and the “DT” reaction. (Displayed as unreacted rate (1- _{f f} ).)
The fusion cycle (f) represents the number of fusions generated per second.
When the fusion cycle (f) is doubled to 2000 times per second, the density of slow particles (ρ) is the same, and the number of slow particles and the slow ion current ( _IL ) launched in 1 second are both double It becomes. The particle number of the fast particles and the fast ion current (I _H ) are the same and the number of particles per bunch is one half.
Therefore, if the fusion period (f) is increased, the decrease of low-speed particles due to collisions will be reduced, so it can be expected that the fusion reaction rate (η _f ) can be maintained high, but fuel particles including particle accelerators (62) etc. There is an upper limit because it is necessary to shorten the length of the circulation path (69).

Table 4 Fusion reaction rate calculation table

The fusion reaction rate (η _f ) of "D-D" reaction and "D-T" reaction and "tritium annihilation cooperative reactor" are examined.
As the DD reaction cross section (σ) is as small as 0.13 barns (0.13 × 10 ^-24 cm ² ), the fusion reaction rate (η _f ) is around 50%, so In the calculation table 4 above, this problem is avoided by setting it to twice (2.91 × 10 ²⁰ ) the number of particles (1.45 × 10 ²⁰ ) that require high-speed charged particles. .
The high speed unreacted fuel particles (49n, D) are decelerated and circulated, and accelerated again to be reused as high speed fuel particles (D).
Of the fusion produced charged particles (49c), tritium (T) is immediately separated and recovered, decelerated to 1 keV or less, and sent to the DT reactor.

Since the DT reaction cross section (σ) for fusion reaction is as large as 5 barns (5 × 10 ^-24 cm ² ), the fusion reaction rate (η _f ) is 99.99% or more, so tritium (T ) Is almost completely extinct.
The effective length (the length at which particles of 99% react) of the fusion reaction region (52) of the DT reaction is as short as about 1 cm.
If the charged particle beam does not collide correctly, a large amount of tritium (T) will be unreacted, so it is always possible to separate and recover unreacted particles (49 n) and try to eliminate tritium (T) again. Need to be configured as

^{Although the 3} He- ³ He reaction was not listed in the calculation table of Table 4, the fusion reaction cross section (σ) was as small as 0.01 barns, and in order to secure a sufficient fusion reaction rate (η _f ) It is necessary to set the density of charged particles one or two orders of magnitude higher.
If the density of the charged particle beam is high, the fusion reaction rate (η _f ) will be much higher, so it is assumed that the density of the beam is increased 10 to 100 times by focusing on 0.1 μm to 0.3 μm. .
The generation rate of neutrons (n) may be considered to be the product of the mixing ratio of foreign atoms contained in the fuel particles, so when the mixing ratio of D particles is 10 ^-9 , the generation rate of neutrons (n) is 10 ^It has an excellent feature of ^{-18, which} is extremely low.

<Direct power conversion>
A conductor can be placed around the passage of the fusion-produced charged particles (49c), and electric energy (E) can be obtained by electromagnetic induction caused by the charged particles passing in the vicinity of the conductor.
As much as converted to electrical energy (E), kinetic energy (K) of the charged particles can be reduced and decelerated.
Neutrons (n) are not subject to direct power conversion because they have no charge.

The fusion product particles fly isotropically from the fusion reaction region (52) headed by the fusion reaction point (51) toward the periphery.
In order to convert the kinetic energy (K) of fusion-produced charged particles (49c) directly into electric power, it is necessary to dispose the regenerative decelerator (67E) without gaps so as to surround the fusion reaction region (52).
Fusion-produced charged particles (49c) spreading from the fusion reaction region (52) toward the periphery are divided and converged for each face of the polyhedron (32), and then led to the regenerative decelerator (67E).
Although FIG. 7C exemplifies a 32-sided body as an example of the polyhedron (32), it may be a polyhedron having a different number of faces, a cylindrical overall shape, or the like.

<Charged particle concentrator>
A method has been proposed for achieving an incorporation angle of ± 60 ° with an aspheric electrostatic field grid electrode (56e) having a concave shape (Patent Document 6), but kinetic energy (K) of fusion-produced charged particles (49c) Is as high as 800 keV to 14 MeV, and the voltage required to converge is also extremely high, which is not practical.
The focal length also varies depending on the velocity of the charged particles and the mass-to-charge ratio (m / z).
FIG. 7 (a) is an explanatory view of a charged particle converger (56) using an inner surface shape of an ellipse.
An ellipse has two foci, and particles originating from one focal point reflect at any point (Λ) inside the ellipse, and their incident angle (θ ₁ ) and reflection angle (θ ₂ ) are equal , Has the property of focusing on the other focus.
By arranging a plurality of charged particle focusing devices (56) having the fusion reaction point (51) of FIG. 7 (a) as the focal point, all directions can be obtained regardless of the mass to charge ratio (m / z) of the charged particles. The spread of charged particles can be shared and converged.

In addition, since the charged particles collide with the inner wall surface of the charged particle focuser (56) at a shallow angle (θ ₁ <10 °), compared to the case where they collide at a right angle or a near right angle, The impact is greatly mitigated.
The wall near the fusion reaction point (51) of the charged particle focusing device (56) overlaps the wall surfaces of the plurality of charged particle focusing devices (56), so the overlapping part (the part drawn by the broken line) The charged particle converger (56) is disposed on each of the constituent surfaces of the polyhedron (32) in a shape in which the wall surface of the polyhedron is removed.

The shape near the fusion reaction point (51) of the charged particle focuser (56) near the focal point is gradually narrowed and the charged particles are converged gradually.
The charged particle concentrator (56) is made of a strong insulator material such as ceramics, and on the outside of it, electrodes (71, # 1 to 3) for removing charge are provided to apply a positive high voltage. Thus, the charge of the fusion produced charged particle (49c) is prevented.
Pulsed high voltage is sequentially applied from the center side to the outer electrodes (71, # 1 to # 3) to remove charged charged particles.
When current flows to the electrode (71) with the passage of the fusion product charged particle (49c), the kinetic energy (K) of the charged particle is reduced, so that a circumferential interdigital electrode where the induced current does not easily flow Shape it.

<Charged particle separator>
FIG. 7 (b) is an explanatory view of a charged particle separator (68x) configured by a fan-shaped magnetic field (68 m).
After converting kinetic energy (K) of fusion-produced charged particles (49c) to electric energy (E) and decelerating the particles, fusion-produced charged particles (49c) are separated by difference in mass-to-charge ratio (m / z) Separate each nuclide.
The charged particles of velocity (v), mass (m) and charge (q) are in the magnetic field (B)
mv ² / r = qvB
Therefore, it rotates at the radius (r) with respect to the plane orthogonal to the magnetic flux (B), and in the electric field (E),
(1/2) mv ² = qE
Therefore, acceleration is performed in the direction of the electric field (E).

表５　質量電荷比（ｍ／ｚ）と回転半径の計算表
　表５に質量電荷比（ｍ／ｚ）と１テスラの磁界中における回転半径の計算表を示す。
　トリチウム（Ｔ）とヘリウム３（^３Ｈｅ）の磁界中の回転半径が異なるから、容易に分離できる。
　核融合生成荷電粒子のトリチウム（Ｔ）と陽子（ｐ）は、磁界中の回転半径が同一であるため、磁界だけでは分離することが難しいが、飛翔速度が違うから荷電粒子分離器（６８ｘ）に達するまでに速度差で分離している。
　また、Ｄ－Ｄ反応とＤ－Ｔ反応を同時に行う場合は、ヘリウム４（^４Ｈｅ）が加わり、２番目に飛翔してくるが、トリチウム（Ｔ）の回転半径とほぼ同一であるから、分離が難しい。
　ヘリウム４（^４Ｈｅ）が飛翔速度差で分離できるように、Ｄ－Ｔ反応をＤ－Ｄ反応の直前に発生させ、最初に飛翔してくる陽子（ｐ）と２番目のヘリウム４（^４Ｈｅ）に対して、外側の電極（７１、＃１）にマイナスの偏向電圧を加え、内側の電極（７１、＃２）にプラスの偏向電圧を加えて、外側に向けて陽子（ｐ）とヘリウム４（^４Ｈｅ）を加速して分離する。

Table 5 Calculation table of mass-to-charge ratio (m / z) and radius of rotation Table 5 shows a table of calculation of mass-to-charge ratio (m / z) and radius of gyration in a magnetic field of 1 Tesla.
Since the radii of rotation in the magnetic field of tritium (T) and helium 3 ( ³ He) are different, they can be easily separated.
The tritium (T) and proton (p) of fusion-produced charged particles are difficult to separate only by the magnetic field because they have the same rotation radius in the magnetic field, but the charged particle separator (68x) because the flight velocity is different. It is separated by the speed difference until it reaches.
In addition, when performing DD reaction and DT reaction simultaneously, helium 4 ( ⁴ He) is added and it flies second, but it is separated because it is almost the same as the radius of rotation of tritium (T). Is difficult.
The DT reaction is generated just before the DD reaction so that the helium 4 ( ⁴ He) can be separated by the flight velocity difference, and the first flying proton (p) and the second helium 4 ( ⁴ He ), Apply a negative deflection voltage to the outer electrode (71, # 1), apply a positive deflection voltage to the inner electrode (71, # 2), and move the proton (p) and helium outward. Accelerate and separate 4 ( ⁴ He).

The regenerative decelerator (67E, # 10) has some limitations because it can be installed at a limited length, and if charged particles are decelerated too much, charged particles separated due to differences in arrival time will be mixed. After that, separation by charged particle separator (68x) is performed.
The smaller the mass-to-charge ratio (m / z), the larger the decelerating effect appears, so the radius of gyration in the magnetic field also differs.
By decelerating the fusion-produced charged particles (49c) separated due to the difference in arrival time within a range where they do not mix again, the strength of the deflection magnetic field and electric field required for the charged particle separator (68x) can be slightly reduced.

The charged particles separated by the charged particle separator (68x) are sent to a regenerative decelerator (67E, # 11 to # 15) to convert kinetic energy (K) remaining in the charged particles into electrical energy (E).
In FIG. 7 (b), the arrangement of the regenerative decelerators (67E, # 11 to # 15) is drawn radially, but the direction of the charged particles is changed by applying magnetic deflection or using a gently curved surface. Therefore, the regenerative speed reducers (67E, # 11 to # 15) can be arranged in parallel or in a circle.

Since the charged particle separator (68x) and the regenerative decelerator (56) can be a path through which the neutron (n) leaks to the outside, the central axis of the regenerative decelerator (67E) is set to the fusion reaction point (51). By removing and mounting the charged particle separator (68x) at the center of the neutron shielding chamber (67s), it is possible to prevent the neutron (n) from leaking linearly. .
When D- ³ He reaction is performed together, 14 MeV high-speed protons (p) are added to the fusion produced charged particles (49c).
Since the scattered particles (49s) generated at the time of collision of the charged particles and charged particle beam which are neutralized are slower than the fusion produced charged particles (49c), the innermost regenerative decelerator (67E, # 15) Led.

The mass of the fusion product charged particle (49c) entering the charged particle separator (68x) is as small as 0.1 to 0.5 mg / banch, but the speed is as high as 7,000 to 53,000 km / s Thus, the impact force at the time of collision reaches 10 kgf to 30 kgf.
The fusion period (f) is in the audible frequency range and emits acoustic noise due to the reaction of deflection.
To reduce the impact force and acoustic noise by shortening the repetition period of the fusion cycle (f), thereby reducing the fusion product charged particles (49c) per bunch beyond the audio frequency range Can.
In FIG. 7 (b), although it is bent by 80 ° or more, separation of particles is possible with a smaller bending angle, and impact force is obtained by deflecting fusion-produced charged particles (49c) in the opposite direction after separation. To reduce acoustic noise.

<Regenerative reduction gear>
It is made of a cylindrical, tough ceramic or the like that can withstand irradiation of charged particles, forms an electrode electromagnetically coupled to the charged particles on the outside, and converts kinetic energy (K) of the charged particles directly into electrical energy (E).

When the D- ³ He reaction occurs at a rate of 1000 times per second and the number of fusion-produced charged particles (49c) is 7.28 × 10 ¹⁹ / sec, the charged particle flow of proton corresponds to a current of 11.7 A Since the number of protons of one charged particle bunch is 7.28 × 10 ¹⁶ , it is equivalent to 1000 positive charges of 0.0117 coulombs per second passing at a speed of 53,000 km / s. (It passes 1m in about 20ns.)
A charged particle flow of helium 4 ( ⁴ He) corresponds to a current of 23.3 A, equivalent to passing a positive charge of 0.0233 coulombs per second 1000 times at a speed of 13,300 km / s.

When transmitting 200 MW of power, if the voltage is 50kV DC, handle 4kA of current.
Of the total power of 215 MW in the D- ³ He reactor, the proton (p) has 172 MW and helium 4 ( ⁴ He) has 43 MW of kinetic energy (K).
When regeneration is performed using a 300 element regenerative decelerator (67E) of 32 systems, each element carries an electric power of about 56 kW, and each element handles 50 kV and a maximum of 1.2 A as an average current.
Since the induced current induced in each element is in the form of pulses (10 ns to 100 ns / 1 ms) with a large waveform ratio, it is necessary to use an element that can withstand peak voltage and peak current.

FIG. 8A shows a three-element electrostatic coupling type regenerative speed reducer (67e). An electrode (71) performing electrostatic coupling is formed on the outside of the cylindrical container.
When the charged particle bunch approaches, the rectifier (67d +) connected to the electrode (71) and the positive electrode (+) conducts, and the electrode is biased to +25 kV. When the charged particle bunch moves away, a rectifier (67d-) connected to the electrode (71) and the negative electrode (-) conducts, and the electrode is biased to -25 kV.
The electrodes (71, # 1, # 2) of the two elements approach one and move away from the other. Since a decelerating electric field of 50 kV is formed in the gaps of the electrodes (71, # 1, # 2), the fusion charged particles (49c) are decelerated.
Very thin positive and negative pulse-like power is obtained for each electrode (71), and the output of the multiple-stage electrode (71) is rectified, synthesized, and smoothed to obtain DC electrical energy (E) obtain.

FIG. 8 (b) shows a magnetic coupling type regenerative reducer (67 m).
An electrode (71) magnetically coupled with a magnetic body (72, including the case where the relative permeability (μ / μ ₀ ) is 1) is formed outside the cylindrical container.
Pulsed power is obtained to the electrode (71) magnetically coupled to the flow of charged particles by electromagnetic induction, and the rectifiers (67d +, 67d−) conduct, rectify and smooth, thereby direct-current electrical energy (E) obtain.
The coupling to the charged particle bunch is determined by the permeability (μ) of the magnetic body (72), the length of the electrode (71), etc., and the amount of electrostatic coupling and magnetic coupling are larger for the regenerative decelerator (67E) in the latter stage. Do.
The actual regenerative decelerator (67E) is in a coupled state in which the magnetic coupling type (67m) and the electrostatic coupling type (67e) are superimposed on each other, and (a) and (b) in FIG. The arrangement of the rectifiers (67d +, 67d−) considered.

FIG. 8C is an example in which a resistor (67R) is connected as a load of the regenerative reduction gear (67E).
The resistor (67R) can be heated at a position away from the regenerative decelerator (67E) to convert kinetic energy (K) of the charged particles into thermal energy (Q).
The electrode (71) itself may be a resistor (67R).
There is also a configuration method that does not use direct power conversion, in which a resistor (67R) is connected to the regenerative speed reducer (67E) to convert it into thermal energy (Q) to integrate thermal power generation.
For thermal power generation, calculation is shown with a thermal efficiency (η _Q ) of 60% (T _H = 750 ° C.), but the thermal output can be raised to the heat-resistant temperature of the heat exchanger. From η _Q ), a thermal efficiency (η _Q ) higher than 80% can be expected if the high temperature source (T _H ) is 1300 ° K and 77%, and if the high temperature source (T _H ) is 1800 ° K.
η _Q = 1-(T _L / T _H )

When the charged particle bunch passes the electrode (71, # 1), the charged particles of the tail of the bunch are attracted to the electrode (71, # 1) biased to -25kV, so some charged particles are the electrode (71, # 1). 1) Remain around or charge.
When the next charged particle bunch approaches, the electrode (71, # 1) is biased to +25 kV, and the remaining (charged) charged particles are repelled, but cause mixed charged particles of different nuclide. (Since the nuclide is not separated in the simplified reactor (50s), no problems occur even if it is mixed.)
At the timing when the end of the charged particle bunch passes through the electrode (71, # 2) and the electrode (71, # 2) changes to -25 kV, the switch (67sw) of the electrode (71, # 1) is turned on to By biasing 71, # 1) to +25 kV, the residual or charged particles are repelled in the direction of the electrodes (71, # 2) to prevent mixing of the nuclide of the charged particles.

The charged particle bunch is decelerated each time it passes each element of the regenerative decelerator (67E) and loses kinetic energy (K). The amount of electrical coupling and magnetic coupling are increased, and the outputs of the individual elements are designed to be equal.
The position of the regenerative decelerator (67E, # 1 to # 32) is adjusted to shift the arrival time of the fusion-produced charged particle (49c) to avoid concentration of the regenerative power peak.
There is also a configuration method in which the same regenerative decelerator (67E) is circulated many times.

<Neutron Heat Exchange Room>
FIG. 9A is an explanatory view of the heat conversion chamber (67Q).
The heat conversion chamber (67Q) has a spherical shell shape as a whole and is composed of a plurality of neutron heat converters (67c) and a neutron shield (67s), each of which is a polyhedron (32) as shown in FIG. 9 (c) It is configured to be divisible into regions corresponding to the respective faces of.
Neutron (n) generated by fusion penetrates the wall of the charged particle concentrator (56) and heat energy is generated by the neutron heat converter (67c) and the neutron moderator (10) filled in the neutron shielding chamber (67s) Convert to (Q), slow down and absorb. The neutron moderator (10) uses water.

The neutron heat converter (67c) is located inside the neutron shielding chamber (67s), filled with pressurized neutron moderator (10), and decelerates 90% or more of fusion generated neutrons (n) Absorb and convert to thermal energy (Q). (Non-patent document 5)
The neutron thermal converter (67c) secures a thickness of the neutron moderator (10) of 50 cm or more, provides a through hole for securing the flow path of charged particles, has a shape that withstands high pressure, upper and lower by connecting pipe (67j) And circulate the neutron moderator (10) upward.

The neutron shield (67s) is filled with an atmospheric pressure neutron moderator (10) and decelerates less than 5% of neutrons (n) transmitted through the neutron thermal converter (67c) to convert it into thermal energy (Q) And absorb neutrons (n) and shield them.
The neutron shielding chamber (67s) is shaped to increase the volume in the extension direction to ensure shielding since neutrons (n) pass through the opening where the fuel particle is injected and the regenerative decelerator (67E) is installed. .
It can be removed for maintenance work, and the neutron shielding chamber (67s) has an angle different from the radiation direction of neutrons (n) to reduce leakage between adjacent neutron shielding chambers (67s). It has a multistage shape to match.

表６　中性子線量計算表
　表６は連携炉（５０ｃ）と簡易炉（５０ｓ）の中性子線量計算表である。
　どちらも１～４日で一般人の年間被爆許容量（１ｍＳｖ／年）に達する。
　図４に示す２００ＭＷのＤ－Ｄ及びＤ－Ｔ反応を行う連携炉(５０ｃ)では、それぞれ、１４．６×１０^１９個の２．４５ＭｅＶ及び１４ＭｅＶの中性子が発生し、半径２０ｍの地点で、厚さ５ｍの水の層を透過する中性子（ｎ）の実効線量は、係数を考慮して、１日当たり０．２７７ｍＳｖである。（この計算表では、全て１４ＭｅＶの中性子とした。水の厚さを６ｍとすると、一般人の年間被ばく許容量に抑えられるが、荷電粒子分離器（６８ｘ）、回生減速器（６７Ｅ）などの収容部分の水の厚さが減少するから、５ｍとした。）熱交換室（６７Ｑ）には貫通部分が多く、透過する中性子（ｎ）が存在する。
　稼働中は周辺に立ち入ることが出来ず、外側に厚さ１ｍ以上の外壁（５９）を設け、一般人の年間被ばく許容量以下になるよう、中性子（ｎ）を遮蔽する。
　軽量な中性子反射体（６７ｂ）を内蔵して中性子減速材（１０）を減すとともに、低放射化フェライト鋼など強靭な構造材が必要であり、これらは、中性子遮蔽体・反射体として算入することができる。
　また、発熱量が少ない外側の中性子遮蔽室（６７ｓ）の一部は、軽量な固体の中性子遮蔽体（６７ｐ）などに置き換えることができる。

Table 6 Neutron dose calculation table Table 6 is a neutron dose calculation table of the cooperative reactor (50c) and the simple reactor (50s).
Both reach the annual exposure allowance (1 mSv / year) of the general public in 1 to 4 days.
In the cooperative reactor (50c) performing 200 MW DD and DT reactions shown in FIG. 4, 14.6 × 10 ¹⁹ 2.45 MeV and 14 MeV neutrons are generated, respectively, at a point of 20 m in radius The effective dose of neutrons (n) permeating the 5 m thick water layer is 0.277 mSv per day, taking into account the factor. (In this calculation table, all neutrons are 14 MeV. If the thickness of water is 6 m, it can be reduced to the annual exposure allowance of the general public, but the charged particle separator (68x), regenerative decelerator (67E), etc. Since the thickness of water in the part is reduced, it is 5 m.) There are many penetrating parts in the heat exchange chamber (67Q), and the transmitting neutrons (n) exist.
During operation, it is not possible to enter the surrounding area, and an outer wall (59) with a thickness of 1 m or more is provided on the outside to shield neutrons (n) so as to be below the annual exposure tolerance of the general public.
A lightweight neutron reflector (67b) is incorporated to reduce the neutron moderator (10) and a strong structural material such as low activation ferritic steel is required, and these are included as neutron shields and reflectors. be able to.
In addition, a part of the outer neutron shielding chamber (67s) having a small calorific value can be replaced with a lightweight solid neutron shielding body (67p) or the like.

A neutron multiplier made of a material containing beryllium (Be) or beryllium (Be) is placed in a neutron shield (67s) to absorb high-energy neutrons (n) and generate new neutrons (n) be able to.
9Be + n → 2 ( ⁴ He) + 2 (n)-2.5 MeV
The doubled neutrons (n) react with the neutron moderator (10) in the neutron heat converter (67c) to form deuterium (D) and tritium (T).
p + n → D + γ 1.67 MeV
D + n → T + γ
By regularly purifying the neutron moderator (10), it is possible to recover more fusion fuels such as deuterium (D) and tritium (T).

<Neutron of a simple reactor>
In the simplified reactor (50s) performing only the 200 MW D- ³ He reaction shown in FIG. 5, although in principle no neutron (n) is generated, D particles or T in the helium 3 ( ³ He) of the fusion fuel When the particles are mixed, a fusion reaction that generates neutrons (n) occurs.
When the contamination rate is 10 ^-12 , the effective dose of neutron (n) is calculated as shown in Table 6, when calculated as having the same shielding effect as a 50 cm thick water layer at a point of 10 m in radius Is 0.813 mSv per day.

Since neutron (n) reacts with the fusion fuel helium 3 ( ³ He), it changes to tritium (T), so it is necessary to pay attention to the fuel storage method.
³ He + n → T + p + 0.764 MeV
The neutron emission rate of the simplified reactor (50s) depends on the content of impurities in the fusion fuel, so well-refined fusion fuel is used, and it is possible not only to avoid irradiation with neutrons (n), but also to store it. Just before collision with helium 3 ( ³ He) of fusion fuel, heteronuclear (49s, D particles, T particles) due to difference in mass-to-charge ratio (m / z) when bent by an ion bending device (68r) or the like Etc.) is important.
The effect of separating and removing heteronuclear nuclei (49s, D particles, T particles, etc.) is large, and if the mixed ratio of hetero atoms is reduced to 1/1000, the 50 cm thick neutron shielding chamber of the neutron moderator (10) ( 67s) can be reduced.
In the case of mobile units, the load factor and operating time of the furnace can be taken into account.
There is also a method of providing a shield plate made of a material having a large neutron shielding effect between the occupant and the fuel tank.

<Blanket>
The blanket used in the magnetically confined fusion reactor uses lithium (Li), beryllium (Be), etc., which have a large neutron reaction cross section (σ _n ), and propagates tritium (T), which is a fusion fuel, Shield neutrons (n).
Since lithium (Li) has excellent shielding ability against neutrons (n), the thickness of the neutron moderator (10) can be reduced. (Non-patent document 6)
A reaction formula for absorbing neutron (n) to form a fusion fuel such as tritium (T) or doubling neutron (n) is shown below.
⁶ Li + n → T + ⁴ He + 4.8 MeV
⁶ Li + n → n + D + ⁴ He-1.5 MeV
⁷ Li + n → n + T + ⁴ He-2.5 MeV
⁹ Be + n → 2 ( ⁴ He) + 2 (n)-2.5 MeV
⁹ Be + ⁴ He → ¹² C + n
In addition to solid lithium compounds (Li ₂ O, Li ₂ TiO ₃ , LiH) and the like, use of liquid metal lithium (Li, LiPb) and the like as tritium breeders is also studied.
By using beryllium (Be), a beryllium compound (Be ₁₂ Ti) or the like as a neutron doubling agent, it is possible to increase the yield of tritium (T) by doubling the neutron (n).

(A) When liquid metal lithium (Li, LiPb) is used, the high temperature liquid metal containing the radioactive substance circulated in the blanket is taken out to recover tritium (T), so at the time of an accident It will be difficult to deal with it.
(B) When using a lithium compound containing oxygen (Ki ₂ O, LiOH, Li ₂ TiO ₃ ), about 98% is recovered as tritiated water (HTO molecule), so a separation method using a hydrophobic catalyst, etc. , The process which takes out only tritium gas (13) is required.
(C) a lithium compound containing no oxygen _{(LiH, Li 3 N),} LTZO20 (Li 2 TiO 3 + 20% Li 2 ZrO 3) , etc., is recovered 99% range as tritium gas (13, HT molecule) Therefore, the separation process of tritium (T) is easy. (Non-patent documents 7 and 8)
When the tritium production rate (η _t ), which is the ratio of tritium (T) produced to neutron (n) produced in DD reaction and DT reaction, is 0.5, the output is approximately 1.6 times, 0 .8, it is possible to construct an approximately 3.6-fold tritium multiplier (50 t).

By increasing the neutron multiplier of beryllium (Be) and lead (Pb), the neutron doubling effect of fast neutrons is also increased, and the local formation rate (ト_t ) of tritium (T) is 1.3 to 1. 4 can be configured, and a tritium breeder reactor (50T) having an overall tritium production rate (η _t ) of 1 or more can be configured.
If the formation rate (η _t ) of tritium (T) exceeds 1, tritium (T) continues to increase, so operation can be continued only in the DT reactor. However, in order to prevent accumulation of excess tritium (T), a 10 to 40 cm thick neutron conditioning chamber (67v) for injecting the neutron moderator (10) inside the tritium breeding chamber (67T) is provided, and It is necessary to provide a structure capable of controlling the tritium production rate (制 御_t ) itself by, for example, providing a mechanism for blocking the neutron (n) to be reached.
The DD reactor can be omitted, and the operation mode is such that tritium (T) in circulation is recovered at the time of stop and stored as fuel for the next start.
Since the fusion reaction rate (η _f ) of the D-T reaction is large, the particle density (を) of the low-speed fuel particles deuterium (D) can be reduced, and the requirement for the particle accelerator (62) is also It is lowered.
Furthermore, since the particles that fly in the DT reaction are only neutron (n) and helium 4 ( ⁴ He), there is no need for a charged particle separator (68 x).
The addition of the resistor (67R) to the regenerative speed reducer (67E) is characterized in that the heat conversion type configuration is easy.

Fig. 9 (b) shows a thermal system in which a tritium breeding chamber (67T) filled with a material containing lithium (Li) and beryllium (Be) used in the blanket of a magnetically confined nuclear fusion reactor is added to the cooperative reactor (50c) It is the configuration of the exchange room (67Q).
The tritium breeding chamber (67T) is filled with a lithium compound (LTZO20), which is a tritium breeding material, and beryllium (Be), which is a neutron multiplier, and the upper and lower tritium breeding chambers (67T) are connected by a connecting pipe (67j). ing.
Helium 4 gas (24) to which about 1% of hydrogen gas (11, 12) is added is refluxed to recover particles (D, T, ⁴ He, C) generated by irradiation of neutron (n) Do.
The thermal energy (Q) contained in the recovered high temperature gas is recovered, power is generated by heat, and electrical energy (E) is obtained.
The recovered circulating gas contains about 1% of hydrogen and other gases (11, 12) and about 0.01% of tritium gas (13) with respect to helium 4 gas (24), carbon (C) and these Fine powders such as compounds of the present invention and propagation materials are mixed.
Gases such as hydrogen (11, 12, 13) are concentrated using a hydrogen separator (82a) using a palladium alloy membrane (an alloy in which a small amount of Ag, Pt, Au or the like is mixed with Pd) having a large hydrogen permeability coefficient.
In addition to the method using a hydrogen separator (82a) using a hydrogen permeable membrane, a hydrogen storage alloy (79m) such as a palladium alloy having a high hydrogen storage capacity stores hydrogen gas (11, 12, 13) and heats it There is also a method of concentrating a gas such as hydrogen using a hydrogen separator (82b) to be released.
Concentrated hydrogen and other gases are sent to a charged particle generator (61), ionized, and only tritium (T) is selected according to the mass-to-charge ratio (m / z), and nuclei are generated using tritium (T) as fuel by DT reaction. Fusion reaction.
A method of liquefying the recovered gas and separating it by utilizing the difference in boiling point is also conceivable.

Since it takes time to recover tritium (T) in the tritium breeding chamber (67T), it takes 20 minutes for the reflux gas to go around. The amount of tritium (T) produced in 20 minutes exceeds 0.4 g.
This is more than one million times the amount of tritium (T) instantaneously present in comparison with the cooperative reactor (50c) without the tritium breeding chamber (67T).
The price of lithium (Li) per unit mass is less expensive than deuterium (D), but safety measures for the tritium multiplier (50 t) and the tritium breeder (50 T) are extremely important.

<Stop of Tritium Multiplier>
The shutdown of the tritium multiplication furnace (50t, limited to ones with DD furnace) requires time for recovery of tritium (T) in the tritium breeding chamber (67T) even after completely stopping the DD reaction. Therefore, it is necessary to continue the extinction operation (DT reaction) while circulating tritium (T), and the generation of tritium (T) by neutrons (n) generated by the tritium annihilation operation continues.
The circulating tritium (T) is designed to decrease with time, but even if the formation rate (η _t ) is 50%, the amount of tritium (T) is reduced by a factor of 10 or more for 1/10 Since it requires, the elimination operation of tritium (T) for six hours or more is required.

When multiple tritium multipliers (50t) are in operation simultaneously, provide a cavity with a thickness of 10 to 40 cm into which the neutron moderator (10) is injected, and reach the tritium breeding chamber (67T) at shutdown (n) In the case of a configuration that blocks H, it is possible to eliminate tritium (T) without newly generating tritium (T), so the time required for stopping can be shortened.

<Scale of fusion reactor>
The simple reactor (50s) can also be configured as an aircraft or space shuttle engine.
The thrust of one large aircraft corresponds to approximately 200 MW.
The 200 MW cooperative reactor (50c) consumes 38.45 kg of deuterium (D) (heavy water 192.5 kg) annually, so the 200 MW cooperative reactor (50 c) can meet the total power consumption of 1000 TWh in Japan. If it consists of 570-1000, it will need 570-1000 and consume as much as 110 tons of heavy water a year. (When not using D- ³ He reaction)
When converted to natural water, it is more than 730,000 tons, which is a huge amount of water.
If the D- ³ He reaction is also used, the consumption of heavy water is reduced to half at 65.9 t, but it is still considerable.

In the case of a simple furnace (50 s) using only 200 MW D- ³ He reaction, it consumes 7.69 kg deuterium (D) (heavy water 38.45 kg) and 11.54 kg helium 3 ( ³ He) annually The annual consumption of 4.39 tons of deuterium (D) (heavy water 22 tons) and 6.58 tons of helium 3 ( ³ He) can cover the total power consumption of Japan.
A tritium breeder consisting only of a DT furnace can be operated using 7.69 kg of deuterium (D) and 26.9 kg of lithium (Li) as fuel annually.
Helium 3 ( ³ He) from the moon etc. rather than constructing a cooperative reactor (50c), a multiplier (50t), and a breeding reactor (50T) that are activated by neutrons (n) and handle dangerous tritium (T) From the viewpoint of procurement and resource protection, we think that a simple reactor (50s) using only safe D- ³ He reaction should be constructed.

It is possible to realize fusion power generation at a stretch by giving up on plasma type nuclear fusion that does not progress slowly.
Perform “D-D reaction”, then “D-T reaction” to produce helium 3 ( ³ He), “ ^triple breeder reactor (50c)” to eliminate tritium (T), tritium breeder reactor with lithium blanket By the like (50t, 50T), huge amount of energy can be obtained.
The “simple reactor (50s)” performing the D- ³ He reaction can obtain energy (E, Q) equivalent to that of the “joint reactor (50c)” and is a nuclear fusion that does not contain radioactive substances, so it can be transferred It can also be used as a propulsive force for the body.

Behavior of fusion particle of DD reaction Behavior of fusion particles of D-T reaction Behavior of fusion particle of D- ³ He reaction Tritium annihilation type of charged particle beam collision type fusion reactor (D-D, D-T reactor) Simple type charged particle beam collision type fusion reactor (D- ³ He reactor) Flight (a) to (e) DD reaction of fusion formed particles, (f) DD and DT reactions (A) charged particle focusing device, (b) charged particle separator, (c) polyhedron Regenerative reduction gear (a) electrostatic coupling type, (b) magnetic coupling type, (c) resistor load type (A) Neutron heat conversion chamber, (b) Tritium breeding chamber Simple type charged particle beam collision type fusion reactor (Example 1) Heat conversion type charged particle beam collision type nuclear fusion reactor (Example 2) (a) Longitudinal sectional view, (b) transverse sectional view, (c) Fusion power generation device configured with thermal conversion reactor Tritium annihilation cooperation type charged particle beam collision type nuclear fusion reactor (Example 3) (A) Ion current bender, (b) Ion neutralizer (A) Circulation of the neutron moderator of the tritium annihilation cooperative reactor (Example 3), (b) Circulation of tritium of the tritium multiplier (Example 4) Circulation of tritium in tritium breeder reactor (Example 5)

Example 1: Simple Reactor
FIG. 10 is a block diagram of a simplified (50s) charged particle beam collision type nuclear fusion reactor (50) of the first embodiment.
As the collision method of charged particles, one is a low charge particle beam with a large number of particles of diameter 2 μm of Deuterium (D) which is easily available, and the other is a small number of particles with a diameter of 1 μm of helium 3 ( ³ He) The charged particle beam is collided at high speed, and the charged particle is fusion-reacted without waste.
The charged particle beam generator (60, # 01) for low speed includes a charged particle generator (61, # 0), a particle accelerator (62, # 01, # 02), and an electron lens (63) for focusing a charged particle beam. And a deflector (64) for adjusting the beam direction, and further, an ion recovery path (68c) and a regenerative decelerator (67E, # 00), an ion transport path (68), an ion flow bender The fuel particle circulation path (69, # 0) which is configured by (68r) is configured.
The charged particle beam generator (60, # 11) for high speed includes a charged particle generator (61, # 1), a particle accelerator (62, # 11, # 12), and an electron lens (63) for focusing a charged particle beam. And a deflector (64) for adjusting the direction of the beam, and further, a fuel particle circulation passage (69, # 1) comprising an ion transfer passage (68) and an ion flow inflector (68r).

The deuterium gas (12) and helium 3 gas (23), which are fusion fuels, are ionized by the charged particle generator (61, # 0, # 1) and the charged particles are accelerated by the particle accelerator (62, # 00, # 10) Accelerate to 0.1 keV to create a bunch of pulsed charged particle beam, and send it to the fuel particle circulation path (69, # 0, # 1) consisting of the ion transport path (68) and the ion flow bender (68r), The final acceleration is performed by the particle accelerator (62, # 01, # 11).
The slow beam with many particles is fired first, then the fast particle beam with a time lag.

The velocity of the charged particle beam to be emitted is a relative velocity (low speed beam: 1 keV, 300 km / s, high speed beam: 400 keV, 5000 km / s) at which the fusion reaction cross section (σ) determined by the combination of fusion fuels becomes large. .
In the elongated fusion reaction area (52) headed by the fusion reaction point (51), the launch time and direction and the tilt of the bunch are adjusted so that the entire bunch collides.
Heteronuclear nuclei (49s) such as deuterium (D) and tritium (T) mixed in fuel helium 3 ( ³ He) cause neutron (n) generation.
The ion flow bender (68r) is capable of passing through the ion flow bender (68r, # 11, # 12) because particles of nuclides outside the transfer purpose are ejected at an angle different from the basic bend angle. Remove alien nuclei (49s) as long as possible. (Heteronuclear contamination: 10 ^-12 or less)
The separated heteronuclear nuclei (49s) give electrons of the electron generator (70e), are returned to gas by the ion neutralizer (70, # 0), and are collected in the gas cylinder (79, # 0).

Unreacted fuel particles (49n) that have passed without performing a fusion reaction are recovered from the ion recovery path (68c) provided at the lower part of the fusion reactor vessel (58) with only low-speed D particles, and regenerative deceleration Is decelerated to 0.1 keV by the probe (67E, # 00), and passes through the fuel particle circulation path (69, # 0) constituted by the ion flow bender (68r, # 04, # 05) and the ion transfer path (68) Then, it circulates to the particle accelerator for low speed (62, # 01) and recycles the unreacted fuel particles (49n).
The ion flow benders (68r, # 01, # 05) are not shown in the figure, but have a structure that combines the flows of charged particles from the regenerative decelerators (67E, # 00) and the particle accelerators (62, # 00). There is a need to.

Since fusion-produced charged particles (49c, p, ⁴ He) produced by fusion go out of fuel particle beams of 1 μm and 2 μm in diameter in a very short time, they are isotropic without colliding with other fuel particles. It flies and reaches the periphery of the fusion reactor in the order of fast p particles and ⁴ He particles.
Converged by charged particle concentrators (56, # 1 to 32), which are arranged without gaps so as to share and surround each face of the polyhedron (32), by 300 elements of regenerative decelerators (67E, # 1 to 32) Then, the kinetic energy (K) of the charged particles is directly converted to electric energy (E).
The simple type (50s) charged particle beam collision type fusion reactor (50) does not need to have a charged particle separator (68x) because the fusion produced particles do not contain dangerous substances such as tritium (T) .
Since all fusion-produced charged particles (49c) are final fusion-produced particles (49f, p, ⁴ He), the electron neutralizer (70, # 1 to 32) emits electrons from the electron generator (70e) It is given back to gas and collected in a gas cylinder (79, # 0). (Including mixed scattering particles etc.)

The length of the particle accelerator (62) is generally several tens of meters or more, but the lengths of the ion transfer path (68), the particle accelerator (62) and the aforementioned regenerative decelerator (67E) in FIG. I draw it for the convenience of the figure.
The length of the ion transfer path (68) corresponds to the fusion generation period (1 ms) in consideration of the transit time of the particle accelerator (62), the transfer rate of charged particles in the ion transfer path (68), etc. I have to.
The low-speed particle accelerator (62, # 01, # 02) and the high-speed particle accelerator (62, # 11, # 12) have a two-stage configuration.

Although not shown in FIG. 10, the ion recovery path (68c) is provided with a sensor for detecting the arrival position of high-speed and low-speed charged particle beams and the amount of particles, and data necessary for controlling collisions etc. I have acquired.
In addition, the container of the charged particle focusing device (56) is provided with a role of a vacuum container (55), and helium 4 gas (24) etc. is circulated as a heat removal chamber (67a) around it to perform heat recovery.
The heat circulation mechanism and the thermal power generation mechanism are not shown in FIG.

<Stop procedure>
The stop of the simple type (50s) charged particle beam collision type fusion reactor (50) stops the charged particle generator (61, # 1) and stops the high speed charged particle beam.
Next, the charged particle generator (61, # 0) is stopped.
The circulating low speed charged particle beam changes the deflection intensity of the ion flow inflector (68r, # 04) and sends it to the ion neutralizer (70, # 0) to give electrons and neutralize it, and the gas cylinder Recover to (79, # 0) and shut down the furnace.

<Example 2: Heat conversion furnace>
FIG. 11 is an explanatory view of a heat conversion type (50 h) charged particle beam collision nuclear fusion reactor (50) of the second embodiment.
As the collision method of charged particles, one is a low charge particle beam with a large number of 2 μm diameter particles of Deuterium (D) which is easily available like the simple reactor (50s), and the other is helium 3 ( ³ He) The number of particles with a diameter of 1 μm is made to collide with a high-speed charged particle beam to cause fusion reaction of the charged particles without waste.
FIG. 11 (a) is a longitudinal sectional view, and the entire shape is a truncated cone, and FIG. 11 (b) is a transverse sectional view, a charged particle converger forming a reflecting surface based on a radial elliptical surface rotating to the right (56, # 1 to 10) and an ion circulation decelerator (67l) constituted by a groove of a single thread provided around the same.
The fusion product charged particle (49c) generated in the fusion reaction region (52) is reflected by one surface of the charged particle focusing device (56, # 1 to 10), and each charged particle bunch is provided in the periphery It is led to the ion circulation decelerator (67l) and rotates clockwise in FIG. 12 (b).
A charged particle rectifying plate (56 g, shown by a chain line) is disposed inside the charged particle converger (56) to lead charged particles flying in a direction close to the axis to the ion circulation decelerator (67l). (The charged particle current plate (56 g) is not present in the heat exchange chamber (67Q).)

A bunch of fusion produced charged particles (49c) orbits along a threaded groove provided on the inner surface of the ion orbiting decelerator (67l).
A planar or mesh resistor (67R) is embedded in the wall of the ion circulation decelerator (67l) made of an insulating material, and the current induced by the charged particles flowing in a pulse along the groove is a resistor (67R) Flow and heat up.
Although not shown in the figure, it is possible to embed an electrode in the wall of the ion circulation decelerator (67l) and place a resistor (67R) at a distant position to generate heat.

The latter half of the ion orbiting decelerator (67l) has a closed groove, which is not shown in the figure, but it is surrounded by a magnetic body to form a closed magnetic path, thereby forming a closed magnetic path, 67R) to enhance the magnetic coupling with the induced current.
The groove (closed groove) of the ion orbiting decelerator (67l) avoids the support structure (ion flow bender (68r, # 03), housing portion such as cooler (85), etc.) of the ion recovery path (68c). It is formed as.
The ion flow bender (68r, # 03) uses a magnetic field in which the magnetic field is strengthened toward the outside, reflects the charged particles (49n, 49c) in the same direction regardless of the nuclide, and recovers from the ion recovery path (68c) The unreacted fuel particles (49n) are circulated to the low speed particle accelerator (62, # 01).

Send air or gas to the heat exchange chamber (67Q) to exchange heat through the wall.
A resistor (67R) is also embedded in the charged particle focusing device (56) and the charged particle rectifying plate (56g) to efficiently convert kinetic energy (K) of fusion-produced charged particles (49c) into thermal energy (Q) Do.
Although not shown in the figure, since the regenerative decelerator (67E) is embedded in the wall of the ion circulation decelerator (67l) and can be configured to take out the electric energy (E) by direct power conversion, the particle accelerator (62) Power for driving can be provided.

A heat conversion type (50 h) charged particle beam collision fusion reactor (50) comprising a fuel particle circulation path (69) comprising an ion transfer path (68) and an ion flow inflector (68r) as shown in FIG. 11 (c). Indicates
The configuration of the low speed fuel particle circulation path (69, # 0) is almost the same as the configuration of the simple furnace (50s) of FIG. 10, but since its length is short, low speed charged particles circulate in a short time. The low speed fuel particle circulation path (69, # 0) is circulated until the next high speed fuel particles are fired and collide.
Capillary (63c) was used as an electron lens (63), which emits a charged particle beam of the two fusion fuel particles deuterium (D) and helium ³ (3 the He).

Fusion-produced charged particles (49c) decelerated by the ion circulation decelerator (67l) are collected into the gas cylinder (79) via the ion transfer path (68) and the ion neutralizer (70).
Separate the remaining helium 3 ( ³ He) and the mixed fusion particles (49c) that did not die out with a kicker (68k), and at the time of shutdown deuterium (D) into an ion neutralizer (70) Send it back to gas and collect in gas cylinder (79).

The air or gas sucked from the left side of FIG. 11 (a) is heated in the heat exchange chamber (67Q) and sent to the turbine (86) on the right side to drive the generator (88) to obtain electric energy (E) , Constitute a fusion thermal power generator (81).
Since nuclear fusion using helium 3 ( ³ He) does not generate neutrons (n) and does not generate tritium (T) in principle, there is no need to separate the fusion produced charged particles (49c),
There are few restrictions on the axial length of the charged particle beam bunch, and
The heat conversion furnace (50 h) has an extremely small number of parts and a simple furnace structure.

Although not shown in the figure, application as a fusion jet engine (80j) or the like is also expected.

<Example 3: Cooperative Reactor>
FIG. 12 is a block diagram of a tritium annihilation cooperation type (50c, DD, DT reactor) of the charged particle beam collision type nuclear fusion reactor (50) of the third embodiment.
As the collision method of charged particles, one is a low charge particle beam with a large number of particles of diameter 2 μm of Deuterium (D) which is easily available, and the other is two kinds of Deuterium (D) and tritium (T). A high-speed charged particle beam with a small particle number of 1 μm in diameter is made to collide, and the charged particles are fusion-reacted without waste.
The charged particle beam generator (60, # 00) for low speed includes a charged particle generator (61, # 0), a particle accelerator (62, # 0, # 00), and an electron lens (63) for focusing a charged particle beam. And a deflector (64) for adjusting the beam direction, and further, an ion recovery path (68c) and a regenerative decelerator (67E, # 0), an ion transfer path (68), an ion flow bender The fuel particle circulation path (69, # 00) is formed of (68r), and deuterium (D) which is low-speed unreacted fuel particles (49n) is reused.

The charged particle beam generator (60, # 01) for high speed includes a charged particle generator (61, # 0), a particle accelerator (62, # 0, # 01), and an electron lens (63) for focusing a charged particle beam. , A fuel particle circulation path (69, # 01) comprising a deflector (64) for adjusting the direction of the beam and further comprising an ion transfer path (68) and an ion flow inflector (68r); Deuterium (D), which is unreacted particles (49 n), is reused.
The cooperative reactor (50c) uses deuterium (D), which is easy to obtain, as the first fusion fuel for low speed beams and high speed beams.
Another high-speed charged particle beam generator (60, # 1) is a particle accelerator (62, # 11), an electron lens (63) for focusing the charged particle beam, a deflector for adjusting the beam direction ( 64), tritium (T) generated in DD reaction is separated / decelerated by charged particle separator (68x), regenerative decelerator (67E, # 14 to 324), and it circulates as charged particles as it is ing.

Deuterium gas (12) is sent to the charged particle generator (61, # 0) for ionization, sent to the particle accelerator (62, # 0), and consists of an ion transfer path (68) and an ion flow bender (68r) It is sent out to the fuel particle circulation path (69, # 00, # 01).
Although the length of the particle accelerator (62) is generally several tens of meters or more, the ion transport path (68) and the particle accelerator (62) in FIG. 12 are drawn with a reduced length.
The length of the ion transfer path (68) is determined in consideration of the fusion generation period, the transit time of the particle accelerator (62) and the like.

In the tritium annihilation cooperative reactor (50c, DD, DT reactor), deuterium (D) is used as both a low speed beam and a high speed beam as an easily accessible fusion fuel.
The DD reaction produces tritium (T) and helium 3 ( ³ He), and the tritium (T) is eliminated immediately by the DT reaction.

Helium 3 ( ³ He) is returned to the gas as a safe fusion fuel and accumulated in gas cylinders (79, # 3, 23) to be used as a fusion fuel for the simple reactor (50s).
A D- ³ He reactor is added to the tritium annihilation cooperative reactor (50 c, DD, DT reactor), and helium 3 ( ³ He) is transferred in the state of charged particles and used immediately You can also (Helium 3 ( ³ He) is used as a fuel only during an emergency such as an earthquake, etc., and switching to the D- ³ He reaction is continued, etc.)

A D-D reactor and a D-T reactor, or a D- ³ He reactor may be added to be independent nuclear fusion reactors, or may share a nuclear fusion reactor vessel (58), D- The D and D-T reactions may be alternately generated. Alternatively, the configuration may be such that the slow beam is shared, the DD and DT reactions occur simultaneously, or the DD and DT reactions alternately occur with respect to the circulation of the slow beam.
Example 3 of FIG. 12 is a configuration example in which the fusion reactor vessel 58 of the DD reactor and the DT reactor and the low speed beam are shared.
The D-D and D-T reactions are generated simultaneously (high-speed T particles collide before high-speed D particles), and the number of particles in the shared low-speed beam is the reduction due to the earlier collision reaction. The number of particles shown in Table 4 is considered in consideration.

The particle accelerator (62, # 0) fires two charged particle bunches at 1 keV with a fixed time difference.
By a kicker (68k, # 0) that changes the electric field or magnetic field to change the course of charged particles,
One is sent to the fuel particle circulation path (69, # 00), shaped as a charged particle bunch by the particle accelerator (62, # 00), and launched as a 1 keV slow charged particle beam,
The other one is sent to the fuel particle circulation path (69, # 01), accelerated to 500 keV by the particle accelerator (62, # 01), launched as a high speed charged particle beam, and collided at the fusion reaction point (51) Let

The velocity of the charged particle beam is determined by the combination of fusion fuels. The appropriate relative velocity at which the fusion reaction cross section (σ) increases (the kinetic energy (K At the speed at which) is increased) the entire elongated shaped charged particle bunch is collided to generate a fusion reaction in the elongated fusion reaction area (52) headed by the fusion reaction point (51).
D-D and D-T reactions in the resulting fusion product particles ^{(p, n, T, 3} He, 4 He) , since out of the fuel particle beam very short time the diameter 1μm and 2 [mu] m, other The particles fly isotropically without colliding with the fuel particles, and in the order shown in Table 5, the particles in the order of fast particles, n, p, n, ⁴ He, T, ³ He, in the nuclear fusion reactor vessel (58) Reach the perimeter.

Fusion-produced charged particles (49c) are converged by charged particle concentrators (56, # 1 to 32) arranged without gaps so as to divide and surround each face of polyhedron 32, and a three-element regenerative decelerator (67E, 67) In # 1 to # 32), part of the kinetic energy (K) of the charged particles is directly converted to electric energy (E).
Since asymmetric collisions occur, in the case of DD reaction, one of the fuel particles has a velocity of 0.5 MeV (6,919 km / s), so the flight velocity of the fusion product particles is approximately one half in the same direction. Velocity (250 keV kinetic energy (K)) is added. The kinetic energy (K) of the fusion-produced charged particles (49c) differs between the upper and lower sides of the reactor.

Next, nuclear fusion-produced charged particles (49c) are separated by a charged particle separator (68x), and 8 to 60 elements of regenerative decelerators (67E, p: 60 elements # 11 to 321, ⁴ He: 36 for each nuclide) Direct power conversion is performed by elements # 12 to 322, T: 20 elements # 13 to 323, ³ He: 8 elements # 14 to 324).
Of p, ⁴ He and ³ He of the final fusion product particles (49 f), electrons are given by the ion neutralizer (70, # 1, # 2, # 4) to give gas (11, 24, 23) Return to and collect in gas cylinders (79, # 1, # 2, # 4).
The ion neutralizer (70) is provided with a total of 96 ion neutralizers (70) for each regenerative speed reducer (67E). There is also a method of grouping fusion charged charged particles (49c) for each nuclide and neutralizing them with three ion neutralizers (70), but the ion transfer path (68) and the ion flow bender (68r) Need a lot of

Tritium (T) remains charged particles via a fusion fuel circuit (69, # 1) consisting of a dedicated ion transfer channel (68) and an ion flow bender (68r, # 11 to 13). Then, it is transported to the particle accelerator (62, # 11, T), accelerated to 100 keV, and launched so as to collide with the slow D particle just before the fast D particle collides.
In FIG. 12, only one fusion fuel circuit (69, # 1) dedicated for tritium (T) is drawn, but charged particle concentrators (56, # 1) have the same number as the number of faces of the polyhedron (32). 32) combine multiple ion flow inflectors (68r) and ion transport paths (68) into one charged particle stream and transport it to the particle accelerator (62, # 11, T) .

Unreacted fuel particles (49n) that have passed through the fusion reaction region (52) without fusion, as shown in Table 4, have low fusion reaction rate (η _f ) of D particles, so high speed particles, low speed particles Both particles are recycled and reused.
Unreacted fuel particles (49n) are recovered from the ion recovery path (68c) provided in the lower part of the fusion reactor vessel (58) and reused.
Charged particle generator (61, # 0) in addition to fuel particle circulation path (69, # 00, # 01) for deuterium (D) composed of ion flow bender (68r) and ion transfer path (68) And deuterium (D) supplemented from particle accelerators (62, # 0),
The low velocity unreacted fuel particles (49n, D) are sent to the low velocity particle accelerator (62, # 00),
The non-reacted fuel particles (49n, D) of the high-speed beam are decelerated by the regenerative decelerator (67E, # 0), circulated to the high-speed particle accelerator (62, # 01) and reused.

The high-speed D particles pass the low-speed D particles in the furnace and come out earlier, but because it is after the low-speed D particles to be recycled and fired, the fuel particle circulation path (69, # 01 Take the length of) longer than the fuel particle circulation (69, # 00) and adjust the time difference.
When the collision of the charged particle beam is removed, the amount of deuterium (D) and tritium (T) in the fuel particle circulation path (69, # 00, # 01, # 10) increases too much, so the charged particle generator ( Adjust the particle amount of 61, # 0, # 1).

The ion recovery path (68c) detects the amount, arrival position, and time of charged particle beam particles from voltage, voltage deviation, and time generated in a plurality of annularly arranged electrodes, although not shown in the figure. A sensor is provided to acquire data necessary for grasping the collision state.
The charged particle concentrator (56) is given a role as a vacuum vessel (56), and helium 4 gas (24) is circulated to the heat removal chamber (67a) around it to cool the equipment and recover heat. .

表７　燃料粒子の磁界中の回転半径計算表 <Ion current bender>
FIG. 13 (a) shows an ion bender (68r, # 03, # 08) and an ion neutralizer (70) configured by two fan-shaped magnetic fields (68 m, # 03, # 08) corresponding to FIG. FIG.
The ion flow inflector (68r) causes the flow of the charged nuclide particles to be transferred to bend in any direction by means of a fan-shaped magnetic field and electric field.
Table 7 is a calculation table of the radius of rotation in a magnetic field of 1 Tesla with respect to the velocity of fuel particles.
The ion flow inflector (68r) causes the flow of the charged nuclide particles to be transferred to be bent by a fan-shaped magnetic field.
The basic bending angles of the ion bending device (68r) depicted in FIGS. 10 to 15 are all illustrated as 90 ° views, but this is for convenience of the plan view for explanation, and in fact Design the basic bending angle by the convenience of three-dimensional arrangement.
Because particles of nuclides that are not intended for transport and particles of different velocities are ejected at an angle different from the basic bending angle, purification of the charged particle stream can be performed together.

Table 7 Calculating radius of rotation of fuel particles in magnetic field

Deuterium (D), which is a low-speed fuel particle, is bent in a target direction by an ion flow inflector (68r, # 03) and sent to an ion transport path (68, # 1).
Deuterium (D), a high-speed fuel particle, penetrates the ion flow bender (68r, # 03) and aims at the ion flow bender (68r, # 08) with a stronger fan-shaped magnetic field (68m) And sent to the ion transport path (68, # 2).
The slower particles among the scattering particles (49s) are directed to the inside of the fan-shaped magnetic field (68 m) and are led to the ion neutralizer (70) via the scattering particle separator (68s) without the magnetic field. .
A negative voltage is applied to the grid electrode (73e, # 0) to induce the scattering particles (49s).
Although fusion-produced charged particles (49c) are also mixed in the ion recovery path (68c), they are penetrated through two fan-shaped magnetic fields (68m, # 03, # 08) because of their high speed, and are transferred to the ion neutralizer (70). To reach.

The ion flow inflector (68r) and the ion neutralizer (70) are made of an insulating material such as ceramic to prevent an accident due to the charged particles coming into contact with the electrode.
On the outer surface of the insulating material, although not shown, electrodes (71) are also provided on the pole faces.
Pulsed high voltage is applied to these electrodes (71) to remove charged charged particles during a time period in which the charged particles do not enter.

<Neutralization of ion>
The lower part of FIG. 13A is an ion neutralizer (70, # 0).
Keep the potential of the grid electrode (73e, # 1) at a negative potential from the grid electrode (73e, # 0), and guide the scattering particles (49s) and the fusion generated charged particles (49c) to the nozzle with a narrowed tip It is punched out, neutralized by a microwave discharge type electron generator (70e), and returned to the gas.
The voltage of the grid electrode (73e, # 0, # 1) is divided by high resistance connected in series and added to the voltage dividing electrode 71e, and it is directed to the tip of the nozzle between the grid electrodes (73e, # 0, # 1) It forms an induced electric field.
Since the velocity differs depending on the nuclide, there is also a method of instantaneously adjusting the voltage of the aspheric grid electrode (73e) at each arrival time of particles so that each type of charged particle can stably pass through the flow path narrowed at the tip. is there.
The gas generated by neutralization is drawn by a high vacuum pump (76h) such as a turbo molecular pump and pressurized by a plurality of stages of vacuum pumps (76), though not shown, to obtain gas cylinders (79, # 0). To recover).
Charged particles are ejected into a circular container from a nozzle whose tip is narrowed, and the gas which can not be sucked by the high vacuum pump (76 h) is rotationally moved to prevent the backflow of the neutralized gas.

In any of the ion flow bending devices (68r) shown in FIGS. 10 to 15, extraneous nuclei (49s) mixed in charged particles for bending purpose and occluded gas particles contained in the material facing the vacuum (00) of the furnace are separated. The ion neutralizer (70) is required for all the ion flow inflectors (68r), although it is not shown in the figure, since it is very slight but exhausted.
To the neutralizer (70, # 0), the fusion product charged particle (49c) irradiated to the opening surface of the ion recovery path (68c) is discharged.
These fusion-produced charged particles (49c) and scattering particles / heteronuclears / scattering particles (49s) are collected in a gas cylinder (79, # 0).

FIG. 13 (b) is an explanatory view of the ion neutralizer (70) connected to the regenerative speed reducer (67 E).
An induction electric field is formed by the grid electrodes (73e, # 0, # 1) (the side surface forms an induction electric field directed to the nozzle tip by the voltage dividing electrode 71e), and the nozzle with the tip narrowed is a circular container. The fusion-produced charged particles (49c) decelerated to positrons are bombarded and neutralized by an electron generator (70e) such as a microwave discharge type to be returned to the gas.
Charged particles are ejected from a nozzle whose tip is narrowed, and the gas which can not be sucked by the high vacuum pump (76 h) is rotationally moved to prevent the backflow of the neutralized gas.
In the simplified reactor (50s), the charged particles having passed through the regenerative reduction gear (67E, # 15 to 325) contain a plurality of nuclides, and particles having a low speed are also present. , # 1) make induction by the electric field.
In the cooperative reactor (50c), charged particles that have passed through the regenerative decelerator (67E, # 11 to 324) are limited to one nuclide and enter at a constant velocity after deceleration, so the fixed magnet makes the magnetic field type It can be made to converge by an electron lens (73 m).

表８　核融合生成粒子の回収ガス量の計算表 Table 8 is a calculation table of the amount of gas at the time of gasification of fusion-produced charged particles (49c).
Since tritium (T) and neutrons (n) are not targets for gasification, the volume of gas at one atmosphere is not shown.
When the fusion produced charged particles (49c) are neutralized and gasified, each ion neutralizer (70) of DD reaction and DD reaction is 1.3 to 2.8 ml per second, D- ³ In the He reaction, the gas is 4.1 milliliters per second.
The fusion-produced charged particles (49c) decelerated by the regenerative decelerator (67E) generate around 1/32 of the gas in each of the ion neutralizers (70, # 1 to 32), so the turbo molecular pump Gas cylinders (79, # 0, # 1, # 2, # 2, etc.) are drawn by a high vacuum pump (76h), etc. and pressurized by a plurality of vacuum pumps (76) although not shown in the figure. Recover to # 4). (In the simplified furnace (50s), it will be collected in the gas cylinder (79, # 0) without sorting.)

Table 8 Calculation table for recovered gas volume of fusion product particles

Tritium (T) disappears almost completely under normal operating conditions, but when the charged particle beam deviates without collision, a large amount of tritium (T, about 0.365 μg / banch) circulates, The ion transport path (68, # 3) is bent at a different angle to the deuterium (D) sent to the ion transport path (68, # 2) as shown in the 13 ion flow benders (68r, # 08) Separated into
Particle accelerators (62, # 11) from the ion flow benders (68r, # 08) of FIG. 12 through the ion flow benders (68r, # 15, # 17) and the regenerative decelerators (67E, # 10) Send to and again eliminate tritium (T).

When performing fusion reaction using helium 3 ( ³ He) as fuel simultaneously in one furnace, as shown in Table 7, tritium (T) and the rotation radius in the magnetic field are the same, so it is difficult to separate as it is It is.
It is possible to separate by providing a kicker (68k) because arrival times are different, but the particle velocity of helium 3 ( ³ He) and tritium (T) after regenerative deceleration by the regenerative decelerator (67E, # 10) As it changes and the turning radius in the magnetic field becomes different, it can be separated by the ion flow inflector (68r, # 17).
The larger the mass-to-charge ratio (m / z) (the smaller the mass / charge), the larger the decelerating effect appears.
The ion flow inflector (68, # 17, # 18) is similar to the charged particle separator (68x) in that it has the ability to separate multiple types of charged particles.

The ion flow bending devices (68r, # 17, # 18) perform nuclide separation of charged particles because the amount of separation of heteronuclear nuclei (49s) increases, and neutralizers (70, # 1, # 2, # 2, # 4 ) And transport routes to gas cylinders (79, # 1, # 2, # 4). (Deuterium (D) can not be separated because it has the same mass-to-charge ratio (m / z) as helium 4 ( ⁴ He).
A hydrogen storage alloy (79 m) is incorporated in a gas cylinder (79, # 2, 24) to adsorb deuterium gas (12, D ₂ ) and separate it when taken out. )
When the collision of the charged particle beam is released, the high speed particles of the charged particle generator (61, # 0) are temporarily suspended so that the tritium (T) in the fuel particle circulation path (69, # 1) does not increase too much. It is necessary to work in concert to adjust the amount of D and to suppress the D-D reaction.

<Tritium gas>
The cooperative type (50c) charged particle beam collision type nuclear fusion reactor (50) is a charged particle generator as shown in FIG. 13 in order to secure the disposal method of tritium (T) etc. recovered in the gasified state. (61, # 1) and a particle accelerator (62, # 10) are provided. (In the simplified furnace of FIG. 10, the separation is not performed.)
The gas recovered in the gas cylinder (79, # 0) of the cooperative reactor in FIG. 12 is made into charged particles by the charged particle generator (61, # 1), accelerated by the particle accelerator (62, # 10), and ion flow bending. The vessel (68r, # 18) selects only tritium (T) and sends it to the particle accelerator (62, # 11, T) to annihilate tritium (T).

The other particles (D, ³ He, ⁴ He) are returned to the gas from the ion flow bending device (68r, # 18) with the ion neutralizer (70, # 1, # 2, # 4,), and the gas cylinder (79) , # 1, # 2, # 4).
The ion flow inflector (68r, # 18) is almost equivalent to the charged particle separator (68x) in that it separates for each nuclide.
In the ion bending unit (68r, # 18), occluded gas particles and the like are separated, so that they are collected into gas cylinders (79, # 3) via the ion neutralizer (70, # 3).

<Circulation of neutron moderator>
FIG. 14 (a) shows the circulation of the neutron moderator (10) of the tritium annihilation cooperation type (50c) of the charged particle beam collision type nuclear fusion reactor (50) of the third embodiment.
The normal mode neutron moderator (10) which circulated the neutron shielding chamber (67s) from the bottom to the top to shield the neutron (n) is pressurized by a pressure pump (87), and the neutron heat conversion of the innermost lowermost part Sent to the container (67c).
A plurality of neutron thermal converters (67c) circulate from the bottom to the top and receive strong neutron (n) irradiation to heat them.
The high temperature neutron moderator (10) is removed from the upper neutron heat converter (67c) and the turbine (86) is turned to drive the generator (88) to obtain power.

The helium 4 gas (24), which is not susceptible to neutrons (n), is sent to the heat removal chamber (67a), and the high temperature helium gas (24) reheats the neutron moderator (10) by the turbine (86). It is done in).
The neutron moderator (10) is cooled by the condenser (89), returned to the lower part of the neutron shielding chamber (67s), and circulated again.
The location of the neutron heat converter (67c) irradiated with neutrons (n) has a sufficient strength, and is made of a strong material such as ceramic which has a small neutron reaction cross section (σ _n ) and is hard to be activated.
Water is used as a neutron moderator (10), but since it absorbs neutrons (n) and changes to deuterium (D), it is periodically taken out to extract deuterium (D).

<Stop procedure>
The cooperative (50c) shutdown procedure shuts off the high speed charged particle beam and shuts off a new DD reaction.
After the tritium (T) particles are sufficiently depleted, the slow charged particle generator (61, # 0, D) is turned off.
With the kicker (68k, # 1), deuterium (D) of the low speed charged particle beam circulating is recovered to the gas cylinder (79, # 0) via the ion neutralizer (70, # 0) Stop the cooperative furnace (50c).
Since deuterium gas (12) is used, the method of returning it to fuel gas cylinder (12, D ₂ ) is also conceivable, but since it is a trace amount of gas generated only at the time of stop, gas cylinder together with scattering particles (49s) It is collected to (79, # 0).

<Example 4: Tritium multiplier furnace>
FIG. 14 (b) shows the circulation of tritium (T) of the tritium multiplying (50 t) charged particle beam collision type nuclear fusion reactor (50) of Example 4.
As the collision method of charged particles, one is a low charge particle beam with a large number of particles of diameter 2 μm of Deuterium (D) which is easily available, and the other is two kinds of Deuterium (D) and tritium (T). The configuration is the same as that of the tritium annihilation cooperative reactor (50c) of Example 3 in which high-speed charged particle beams having a small particle number of 1 μm in diameter collide with each other.
In Example 4, the tritium breeding chamber (67T) having a tritium breeding rate (η _t ) of 1 or less, filled with tritium breeding material (LTZO 20) processed into a granular form, was subjected to heat exchange in the cooperative furnace (50c) of Example 3 It is the configuration added to the room (67Q).
Beryllium (Be), which is a neutron multiplier, is added to adjust the tritium growth rate (η _t ).
It receives neutron (n) irradiation and produces tritium (T), helium 4 ( ⁴ He), etc. in the tritium breeding chamber (67T).

The tritium breeding chamber (67T) connects the upper and lower tritium breeding chamber (67T) and refluxes the helium 4 gas (24) to which 1% of deuterium gas (12) is added from the gas cylinder (79, # 4), Tritium (T) generated upon irradiation with neutrons (n) is recovered in the form of hydrogen gas (HT, DT, etc.).
The heat energy (Q) contained in the high temperature gas recovered through the dust collector (83a) is recovered by the heat exchanger (84), and power generation is performed by the turbine (86) and the generator (88). Get (E).
The hydrogen separator (82a) using the hydrogen permeable membrane has the highest activity at 300 ° C. to 400 ° C. Therefore, the heat exchanger (84) passes through the hydrogen separator (82a) using the hydrogen permeable membrane A path is formed back to the heat exchanger (84).
The hydrogen is recovered by the hydrogen separator (82a) and the water liquefied by the dehumidifier (83b) (HTO etc. are also included, so processing is necessary though not shown in the figure), compounds etc. removed The pressure is pumped by the pressure pump (87) to circulate the gas again.
Hydrogen gas (HT, DT, etc.) containing tritium concentrated by a hydrogen separator (82a) using a hydrogen permeable membrane is recovered in a gas cylinder (79, # 0).

The gas (including scattering particles (49s) etc.) recovered in the gas cylinder (79, # 0) is sent to the charged particle generator (61, # 1) to be ionized, and the ion flow bending device (68, # 18) By this, only tritium (T) is selected and sent to the particle accelerator (62, # 11, T).
Since substances other than tritium (T) are separated by the ion flow bender (68, # 18), they are returned to gas by the ion neutralizer (70, # 1, # 2, # 3, # 4, 79, # 1, # 2, # 3, # 4)
Add the tritium (T) recovered from the tritium breeding chamber (67T) to maintain the D-T reaction, and after the tritium (T) is sufficiently increased, reduce the D-D reaction to maintain the amount of power generation Adjust to

<Stop procedure>
After completely stopping the D-D reaction, the kicker (68k, # 1, # 2) is operated after the circulating tritium (T) which decreases with time is sufficiently reduced, and the low speed fuel particles (D) are operated. And send high speed tritium (T) to the ion neutralizer (70, # 0) and shut down the furnace.
After shutdown of the furnace, low speed fuel particles (D) and tritium gas (13) which could not be extinguished are left in the gas cylinder (79, # 0).

Example 5 Tritium Breeder Reactor
FIG. 15 is a block diagram of a tritium breeder type (50T) charged particle beam collision type nuclear fusion reactor (50) of the fifth embodiment.
As the collision method of charged particles, one is a low charge particle beam with a large number of 2 μm diameter particles of deuterium (D) which is easily available, and the other is a high speed with a small number of 1 μm diameter particles of tritium (T). The charged particle beam is made to collide.
The fifth embodiment is configured to include a tritium breeding chamber (67T) having a tritium breeding rate (η _t ) of 1 or more and a neutron adjustment chamber (67v).
Since the D-T reaction is sufficient, the fuel particle circulation path (69, # 01) of the high speed D particle and the charge mass separator (68x) are removed as compared with the multiplier (50t) of Example 4. Can reduce the number of parts.
The recovery path dedicated to tritium (T) of unreacted fuel particles (49 n) is also omitted, and the gas cylinder (79, #) passes through the ion flow bender (68 r, # 04) and the ion neutralizer (70, # 0). It is supposed to be collected in 0).
Although not shown in the figure, the regenerative speed reducer (67E) may be combined with a resistor (67R) to be a heat conversion type.

The charged particle beam generator (60, # 0) for low speed uses a charged particle generator (61, # 0), a particle accelerator (62, # 00, # 01), and an electron lens (63) for focusing a charged particle beam. And a deflector (64) for adjusting the beam direction, and further, an ion recovery path (68c) and a regenerative decelerator (67E, # 00), an ion transport path (68), an ion flow bender The fuel particle circulation path (69, # 0) which is configured by (68r) is configured.
The charged particle beam generator (60, # 1) for high speed includes a charged particle generator (61, # 1), a particle accelerator (62, # 10, # 11), and an electron lens (63) for focusing a charged particle beam. And a deflector (64) for adjusting the direction of the beam, and further, a fuel particle circulation passage (69, # 1) comprising an ion transfer passage (68) and an ion flow inflector (68r).

The deuterium gas (12) and triple water gas (13), which are fusion fuels, are ionized by the charged particle generator (61, # 0, # 1) and the charged particles are accelerated by the particle accelerator (62, # 00, # 10) Accelerates to 1 keV to create a bunch of pulsed charged particle beam, and sends it to a fuel particle circulation path (69, # 0, # 1) consisting of an ion transfer path (68) and an ion flow bender (68r), and a particle accelerator Final acceleration is performed by (62, # 01, # 11).
The slow particle beam, which has a large number of particles, and then the fast particle beam, are directed toward the fusion reaction point (51) with time lag.

The relative velocity at which the fusion reaction cross section (σ) increases, which is determined by the combination of fusion fuels (low speed beam: 1 keV, 300 km / s, high speed beam: 100 keV, 2,520 km / s) I assume.
In the elongated fusion reaction area (52) headed by the fusion reaction point (51), the launch time and direction and the tilt of the bunch are adjusted so that the entire bunch collides.
The fusion product particles (n, 4He) generated by the D-T reaction fly out of the fuel particle beam of 1 μm and 2 μm in diameter in a very short time, so they fly isotropically without colliding with other fuel particles. At the speed shown in Table 5, particles in the order of high speed particles to n 4 He reach the periphery of the fusion reactor vessel (58).

Convergent-produced charged particles (49c) are converged by charged particle concentrators (56, # 1 to 32) arranged without gaps so as to surround fusion reaction points (51), and regenerative decelerators (67E, # 1 to 32) By direct power conversion of a part of kinetic energy (K) of the charged particles to obtain electric energy (E).
A heat conversion type can also be realized by combining the resistor (67R) with the regenerative speed reducer (67E).
The gas is returned to the gas by an ion neutralizer (70, # 1 to 32) and collected in a gas cylinder (79, # 1).

In the heat exchange chamber (67Q), tritium breeding chamber (67T) and neutron adjustment with tritium breeding rate (η _t ) of 1 or more filled with tritium (LTZO 20) processed into granular form and beryllium (Be) which is a neutron multiplier It is the structure which added the room (67v).
The tritium multiplication rate (η _t ) is adjusted with beryllium (Be), which is a neutron multiplier.
Irradiated with neutrons (n) generated by the fusion reaction, tritium (T), helium 4 ( ⁴ He), etc. are produced in the tritium breeding chamber (67T).
The tritium breeding chamber (67T) is connected to the upper and lower tritium breeding chamber (67T) by a connecting pipe (67j), and deuterium gas (12) contained in the gas cylinder (79, # 1) and the gas cylinder (79, # 3) Helium 4 gas (24) to which 1% is added is refluxed to recover particles (D, T, ⁴ He, C) generated upon irradiation of neutron (n) and accompanying compounds etc. as gas Do.
Fine particles such as growth material contained in the recovered high-temperature reflux gas are removed by a dust collector (83a), thermal energy (Q) is recovered by a heat exchanger (84), a turbine (86), a generator (88) To generate electric energy (E).

Water that has been liquefied in the dehumidifier (83b) (HTO etc. is also included, but it is not shown in the figure but separation processing is required separately), compounds etc. are removed, and hydrogen separation using a hydrogen storage alloy (79m) Hydrogen etc. (mainly HT molecule, DT molecule) is recovered in a gas cylinder (79, # 0) with a container (82b), deuterium gas (12) is added and pressurized with a pressure pump (87) to 4 Cycle the gas (24) again.
The hydrogen separator (82b) using the hydrogen storage alloy (79m) has two chambers in which the hydrogen storage alloy (79m, # 1, # 2) is stored in the rotating body, and is periodically rotated (# 1 # 2) The hydrogen gas (D ₂ , HT, DT molecules, etc.) is stored in one (# 1), and the stored gas is released by heating in the other (# 2).

The gas recovered in the gas cylinder (79, # 0) is sent to the charged particle generator (61, # 1) to be ionized, and only tritium (T) is selected by the ion flow inflector (68, # 10). It is sent to the accelerator (62, # 11, T).
Ion flow bending device (68, # 10) because substances other than tritium (T) are separated by an ion neutralizer (70, # 1) by gas return (mainly _H 2, HD, _{D 2),} the Recover to gas cylinder (79, # 3). (It is also possible to completely separate Deuterium (D).)
The neutron adjustment chamber (67v) is provided, and the dose of neutrons (n) irradiated to the tritium breeding chamber (67T) is adjusted by adjusting the amount of neutron moderator (10), and the tritium multiplication rate (η _t ) control.
The neutron adjustment chamber (67v) can be omitted if the surplus tritium (T) can be eliminated, for example, by providing a DT reactor without the tritium breeding chamber (67T) adjacently.

<Stop procedure>
After securing tritium (T) necessary for startup, increase the amount of neutron moderator (10) in the neutron adjustment room (67v) to lower the tritium multiplication rate (η _t ) and annihilate tritium (T) I do.
Stop the charged particle generator (61, # 1) and stop the high speed charged particle beam.
Next, the charged particle generator (61, # 0) is stopped.
The circulating low speed charged particle beam changes the deflection intensity of the ion flow inflector (68r, # 04) and sends it to the ion neutralizer (70, # 0) to give electrons and neutralize it, and the gas cylinder Recover to (79, # 0) and shut down the furnace.

Helium 3 ( ³ He), which is a safe fusion fuel, generates nuclear fusion reaction with deuterium (D, deuterium) and lithium (Li), which are abundant on the earth, as the first fuel and generates electric energy. It is possible to produce nuclear fusion power as well as nuclear fusion engines, which are less likely to be affected by radioactivity, or to produce neutrons (n) or tritium (T) immediately.

# 00-Individual identification number per drawing _f Fusion reaction rate _{Q Q} thermal efficiency _{t t} tritium formation rate μ / μ ₀ relative permeability 密度 density λ e average free path σ fusion reaction cross section σ _n neutron reaction cross section p proton (Hydrogen nucleus) n Neutron m / z mass to charge ratio D deuterium (deuterium nucleus) T tritium (tritium nucleus)
Li Lithium Be Beryllium Pb Lead E Electric energy K Kinetic energy Q Thermal energy U Internal energy 00 Super high vacuum (10 ^-8 Pa) 10 Neutron moderator (water etc.) 11 Hydrogen gas (H ₂ )
12 Deuterium gas (D ₂ , HD) 13 Tritium gas (T ₂ , HT, DT)
23 Helium 3 gas 24 Helium 4 gas
32 polyhedron (truncated icosahedron etc)
³ He Helium 3 (Helium 3 Nucleus) ⁴ He Helium 4 (Helium 4 Nucleus)
49 Charged particle 49c Fusion formed charged particle 49f Final fusion formed particle (p, ⁴ He)
49n Unreacted fuel particle 49s Scattering particle / charged particle / Heteronuclear 50 50 Charged particle beam collision type fusion reactor 50c Tritium annihilation cooperation type (joint reactor)
50t tritium multiplication type (multiplier furnace) 50T tritium breeder type (fermentation furnace)
50s simple type (simple furnace) 50h heat conversion type (heat conversion furnace)
51 Fusion reaction point 52 Fusion reaction zone 53 Reactor center
55 vacuum vessel 56 charged particle focusing device 56 g charged particle rectifying plate
58 Fusion reactor vessel 59 Outer wall 60 charged particle beam generator
61 Charged particle generator
62 Particle accelerator
63 electron lens 63 c capillary 63 e electrostatic electron lens 63 m magnetic field electron lens 64 deflector
64e electric field type deflector 64m magnetic field type deflector 67 energy converter 67E regenerative decelerator 67l ion circulation decelerator 67e electrostatic coupling type regenerative decelerator 67m magnetic coupling type regenerative decelerator 67d +, 67d- rectifier 67R resistor 67sw switch 67Q heat Exchange room 67a Heat removal room 67b Neutron reflector 67c Neutron heat exchanger 67j Connection tube 67p Neutron shield 67s Neutron shielding room 67T Tritium breeding room 67v Neutron preparation room
68 ion transport path 68c ion recovery path 68k kicker 68x charged particle separator 68r ion flow bending device 68b particle recovery unit 68m fan-shaped magnetic field 68s scattering particle separator 69 fuel particle circulation path 70 ion neutralizer 70e electron generator 71 electrode 71e Partial pressure electrode 72 Magnetic body 73e Aspheric grid electrode 73m Magnetic field electron lens 76 Vacuum pump 76h High vacuum pump 79 Gas cylinder 79m Hydrogen storage alloy 80 Fusion propulsion device 80j Fusion jet engine 81 Fusion thermal power generator 82 Hydrogen separator 82a Hydrogen separator (permeable membrane) 82b Hydrogen separator (hydrogen storage alloy)
83a dust collector 83b dehumidifier 84 heat exchanger 85 cooler 86 turbine 87 pressure pump 88 generator 89 condenser

Claims (8)

Of the two fusion fuels that are launched, one is a low velocity, and the other is a high velocity charged particle beam,
What is both deuterium (D), and
Deuterium (D) and tritium (T),
Deuterium (D) and Helium 3 ( ³ He), and
Both are helium 3 ( ³ He),
It is configured to increase the number of charged particles of low speed rather than high speed charged particles,
Particle accelerator (62) which accelerates charged particles which are these fusion fuels by coulomb force into bunch of pulsed charged particle beam, electron lens (63) which converges charged particle beam, and flying direction of charged particle beam High-speed and low-speed charged particle beam generators (60), consisting of deflectors (64)
An energy converter (67) for obtaining kinetic energy (K) of fusion-produced particles, which is disposed so as to surround the fusion reaction region (52) where the charged particle beam collides;
A fuel particle circulation path (69) comprising an ion recovery path (68c) for recovering the charged particle beam, an ion transfer path (68), and an ion flow bender (68r);
The charged particle beam generator (60) sequentially emits a low speed and then a high speed charged particle beam from the charged particle beam generator (60) to converge on the fusion reaction point (51);
Collision at a relative velocity (a velocity at which kinetic energy (K) obtained by fusion increases with respect to kinetic energy (K) required for collisions) at which the fusion reaction cross section (σ) determined by the combination of fusion fuels increases. Generate a fusion reaction in the elongated region,
The kinetic energy (K) of fusion-produced particles that fly isotropically from the fusion reaction region (52) is acquired by the energy converter (67) and decelerated,
Unreacted fuel particles (49n) that have passed through the fusion reaction region (52) from the ion recovery passage (68c) without performing a fusion reaction are recovered, and charged via the fuel particle circulation passage (69). Recirculate to the particle accelerator (62) without stopping in the state of particles, and reuse it
Charged particle beam collision type nuclear fusion reactor (50) characterized by comprising the fuel particle circulation path (69)
Fusion fuels of charged particle beams, one at low speed and the other at high speed,
Deuterium (D) and Helium 3 ( ³ He), and
Both are helium 3 ( ³ He),
In the energy converter (67) for acquiring kinetic energy (K) of fusion-produced particles,
Charged particle collector (56) that collects charged particles by the inner surface shape based on an ellipse
A regenerative decelerator (67E, 67l) having an electrode (71) electromagnetically coupled to the flow of charged particles, and a rectifier (67d +, 67d−),
A fusion product charged particle (49c) flying isotropically from the fusion reaction region (52) in a pulse shape is converged by the charged particle focusing device (56), and kinetic energy (Fc) of the fusion product charged particle (49c) K) is a simple type (50s) that directly converts electric power with the regenerative reduction gear (67E) to obtain DC electric energy (E) and decelerates charged particles.
The charged particle concentrator (56), the regenerative speed reducer (67E, 67l), and the rectifier (67d +, 67d−) are characterized.
Charged particle beam collision type nuclear fusion reactor (50) according to claim 1
Fusion fuels of charged particle beams, one at low speed and the other at high speed,
Deuterium (D) and Helium 3 ( ³ He), and
Both are helium 3 ( ³ He),
In the energy converter (67) for acquiring kinetic energy (K) of fusion-produced particles,
Charged particle collector (56) that collects charged particles by the inner surface shape based on an ellipse
Regenerative decelerators (67E, 67l) with electrodes (71) electromagnetically coupled to the flow of charged particles,
A resistor (67R) for converting electrical energy (E) into thermal energy (Q), and a heat exchange chamber (67Q);
A fusion product charged particle (49c) flying isotropically from the fusion reaction region (52) in a pulse shape is converged by the charged particle focusing device (56), and kinetic energy (Fc) of the fusion product charged particle (49c) K) directly converts electric power with the regenerative reduction gear (67E) to obtain electric energy (E), decelerates charged particles, and flows an electromagnetic induction current to the resistor (67R) to obtain thermal energy (Q) Conversion type (50h) to convert to
The regenerative speed reducer (67E, 67l) and the resistor (67R) are provided.
Charged particle beam collision type nuclear fusion reactor (50) according to any one of claims 1 and 2
Fusion fuels of charged particle beams, one at low speed and the other at high speed,
What is both deuterium (D), and
Deuterium (D) and tritium (T),
Conducting the D-D reaction and the D-T reaction in combination, including those performed in independent furnaces and those performed in one furnace,
In the energy converter (67) for acquiring kinetic energy (K) of the fusion product charged particle (49c),
Charged particle concentrator (56), regenerative decelerator (67E, 67l), and
Charged particle separator (68x) that separates charged particles by nuclide according to charge-to-mass ratio (m / z) by passing fan-shaped magnetic field and electric field, fuel particle circulation path (69) that circulates tritium (T), And
A heat exchange chamber (67) consisting of a neutron thermal converter (67c) filled with a neutron moderator (10) and an neutron shielding chamber (67s) in an energy converter (67) for acquiring kinetic energy (K) of neutrons (n) Equipped with 67Q),
A fusion product charged particle (49c) flying isotropically from the fusion reaction region (52) in a pulse shape is converged by the charged particle focusing device (56), and kinetic energy (K) of the charged particle is reduced by the regenerative deceleration. Directly convert power with the converter (67E) to obtain electrical energy (E) (including those converted to thermal energy (Q) by the resistor (67R)), and decelerate charged particles,
The fuel particles are separated for each nuclide according to differences in particle velocity (arrival time) of fusion-produced charged particles (49c) and differences in charge mass ratio (m / z) by the charged particle separator (68x) Circulating tritium (T) in the state of charged particles by means of a circulation path (69) to a particle accelerator (62) of the D-T reaction,
Neutrons (n) that fly isotropically from the fusion reaction zone (52) into heat energy (Q) by the heat exchange chamber (67Q) and absorb them into the neutron moderator (10) To shield,
Tritium annihilation cooperation type (50c) of a configuration that annihilates tritium (T) immediately,
A heat exchange chamber (67Q) comprising the charged particle separator (68x), the fuel particle circulation path (69), a neutron heat converter (67c) filled with a neutron moderator (10), and a neutron shielding chamber (67s) Characterized by comprising
The charged particle beam collision fusion reactor (50) according to any one of claims 1 to 4.
Fusion fuels of charged particle beams, one at low speed and the other at high speed,
What is both deuterium (D), and
Deuterium (D) and tritium (T),
Conducting the D-D reaction and the D-T reaction in combination, including those performed in independent furnaces and those performed in one furnace,
Heat exchange with tritium breeding chamber (67T) filled with tritium breeder (including lithium (Li) and its compound) in energy converter (67) to acquire kinetic energy (K) of neutron (n) Room (67Q), as well as
A mechanism for circulating tritium (24) and recovering tritium (T), and a hydrogen separator (82) for separating hydrogen gas,
The tritium (T) is multiplied in the tritium breeding chamber (67T) by being irradiated with neutrons (n) that fly isotropically in a pulse from the fusion reaction region (52),
The circulation gas helium 4 gas ( ⁴ He) is circulated, and the gas containing tritium (T) is recovered by the hydrogen separator (82), and the fuel particle circulation path for tritium (T) in the DT reactor ( 69) in addition to tritium multiplication type (50 t)
Characterized by comprising a tritium breeding chamber (67T) having a tritium production rate (率_t ) of less than 1;
The charged particle beam collision fusion reactor (50) according to any one of claims 1 to 4.
Fusion fuels of charged particle beams, one at low speed and the other at high speed,
Deuterium (D) and tritium (T),
An energy converter (67) that obtains kinetic energy (K) of neutron (n), including one that constitutes a single DT reactor and one that links multiple DT reactors Heat exchange chamber (67Q) having a tritium breeding chamber (67T) filled with a material (including lithium (Li) and its compound) and a neutron doubling material (including beryllium (Be) and its compound) ,
A mechanism for recovering tritium (T) by circulating helium 4 gas (24), a hydrogen separator (82) for separating hydrogen gas, and
A mechanism for adjusting the dose of neutrons (n) reaching the tritium breeding chamber (67T) (neutron preparation chamber (67v), D-T having a tritium production rate (η _t ) less than 1 or having no tritium breeding chamber (67T) The reactor is irradiated with neutrons (n) that fly isotropically from the fusion reaction region (52) in pulse form, and the neutrons (n) and tritium (T) are multiplied in the tritium breeding chamber (67T) And
The circulation gas helium 4 gas ( ⁴ He) is circulated, and the gas containing tritium (T) is recovered by the hydrogen separator (82) and used as tritium (T) fuel of the DT reactor,
The tritium breeder (50T) is configured to have a mechanism for adjusting the dose of neutrons (n) reaching the tritium breeding chamber (67T),
Characterized by comprising the tritium breeding chamber (67T) having a tritium production rate (率_t ) of more than 1;
The charged particle beam collision fusion reactor (50) according to any one of claims 1 to 4.
Having a container made of a strong insulator material such as ceramics that prevents charged particles from coming into direct contact with the electrode, and
An electrode (71) for removing charge is provided on the outside of the insulator container, and a high voltage is periodically applied to perform the charge removal operation.
Particle accelerator (62) that accelerates charged particles to be fuel
Capillary (63c) for focusing charged particles to be fuel
Charged particle collector (56) for focusing fusion-produced charged particles (49c),
Regeneration decelerator (67E, including ion orbit decelerator (67l)) to decelerate fusion product charged particle (49c),
Charged particle separator (68x) that separates fusion product charged particles (49c) according to difference in mass-to-charge ratio (m / z),
Ion recovery path (68c) for recovering unreacted fuel particles (49n),
Ion transport path (68) for transporting charged particles,
An ion flow bender (68r) for changing the traveling direction of charged particles;
Any one or more of the ion neutralizers (70) for giving electrons to charged particles and returning them to gas,
The charged particle beam collision type fusion reactor (50) according to any one of claims 1 to 6.
An ion flow bender (68r) that has a fan-shaped magnetic field (68 m, including one having a fan-shaped electric field 68e) and bends charged particles that have entered, and is charged with a different mass-to-charge ratio (m / z) Characterized in that it comprises an ion flow bender (68r) having an ion neutralizer (70) that separates the particles and returns them to a gas,
The charged particle beam collision type fusion reactor (50) according to any one of claims 1 to 7.

Images