JPWO2019138452A1 - Charged particle beam fusion reactor - Google Patents

Abstract

[PROBLEMS] In a plasma-type fusion reactor, it is difficult to separate generated particles, and there is concern about leakage of tritium, and nuclear fusion has not yet been achieved. The charged particle beam collision-type fusion reactor can generate fusion, but it has been said that the particle accelerator has low acceleration efficiency, low collision rate, and cannot reach breakeven. A particle accelerator having high acceleration efficiency is used to circulate unreacted fuel particles, thereby improving the efficiency. Tritium and helium 3 generated in the DD reactor are separated in the form of charged particles, and the tritium is immediately annihilated in the DT reactor to obtain an enormous amount of energy. A simple (50 s) charged particle beam collision type fusion reactor without radioactive materials was devised. We have also devised a tritium multiplication type and multiplication type (50 t, 50 T) charged particle beam collision type fusion reactor that irradiates neutrons to lithium and the like to multiply more tritium and increase the output. [Selection diagram] FIG.

Description

According to the present invention, a fusion fuel available on the ground is made into a charged particle beam and collided to generate a DD reaction and a DT reaction, and neutrons (n) and tritium (T) generated by the fusion are immediately generated. quenched, to produce helium 3 (3 ^{the He),} and, to a fusion reactor without radioactive material using D-3 ^{the He} reaction.

The basic fusion reaction types and reaction equations are as follows.
DD reaction D + D → T + p 4.03 MeV
^{D + D → 3 He + n} 3.27MeV
D-T reaction ^{D + T → 4 He + n} 17.59MeV
D- ³ He reaction ^{D + 3 He → 4 He +} p 18.45MeV
³ He- ³ He reaction ^{3 He + 3 He → 4 He} + 2p 12.86MeV
Table 1 Fusion mass loss calculation table Table 1 shows the total mass of the two types of particles used for nuclear fusion in a tabular calculation table. , The total mass of the two particles after the nuclear fusion reaction, and the difference mass shown in the vicinity of the arrow (the exponent is omitted, but it is ^10-27 kg).
The mass decrease (mass defect) represents the kinetic energy (K) of the fusion-producing particles.
Multiplying the mass of the decrease by c ² can convert it to the unit of energy (J), and further multiplying by 6.24 × 10 ¹⁸ can convert it to the unit of electron volt (eV).

The physical properties of the substance used for nuclear fusion of the present application are as follows.
D: Deuterium / deuterium 0.015% is contained in natural water, and a sufficient amount can be collected as a nuclear fusion fuel.
The energy required for the production of deuterium is dominated by the energy required for the purification of "heavy water", which requires 57 MWh (megawatt hours) of energy to produce 1 kg of heavy water.
T: Tritium, tritium Tritium (T) is considered to be the least toxic radioactive substance that beta-decays with a half-life of 12.3 years, but the danger of internal exposure has been pointed out.
³ He: helium 3
Helium 3 (3 ^He) is a secure fusion fuel which does not generate radiation.
⁴ He: helium-4
Helium 4 (4 ^{the He)} is a stable and safe substance, nuclei are called alpha particles (alpha), proton (p, hydrogen nuclei) with a final fusion product material.

The following are the main types of fusion reactors being studied around the world.
<Those using plasma>
The main fusion methods that use plasma include magnetic confinement, inertial confinement, and electrostatic confinement.They use a particle accelerator to drive charged particles into the plasma and heat the plasma, and fusion. Includes those that attempt to ignite.

Magnetic confinement fusion reactor (tokamak type, helical type, magnetic mirror type, etc.)
Magnetically confined fusion reactors confine plasma with strong magnetic lines of force and attempt to heat the plasma by injecting microwaves or charged particle beams until the temperature at which fusion occurs is reached.
The Institute of Fusion Science said, "In an experiment using a device called a helical type, we succeeded in raising the ion temperature to 120 million degrees Celsius, which is necessary for power generation." I want to achieve it. "
The International Fusion Test Reactor (ITER) is planning to produce 500 MW of heat in 2035.
There is no doubt that fusion will eventually occur if the plasma ion temperature is increased, but there has been information that "a fusion phenomenon has been observed" despite researching for more than 50 years. Not.
Even if nuclear fusion occurs, the danger of using plasma containing a large amount of tritium (T) in the furnace has been pointed out.

Inertial confinement fusion reactor (laser type, heavy ion inertial fusion, etc.)
Inertial confinement fusion reactors place fusion fuel pellets with a diameter of several millimeters at the center of the reactor and irradiate them with powerful lasers and charged particle beams from all directions to compress the fusion fuel into high-density plasma. The idea is to create nuclear fusion.
Uniformly such problems can not implosion listed, and as "sometimes neutrons was observed." However, helium 3 (3 ^He) fusion product particles has not been detected, confirmed nuclear fusion phenomenon It has not been.
Even if nuclear fusion occurs, all of the nuclear fusion fuel in the small fuel pellets will not react, so that tritium (T) or the like must be purified and extracted from the fusion-produced particles.

Electrostatic confinement fusion reactor (Fuser type, Farnsworth type, etc.)
Electrostatic confinement fusion reactors are also known as fuser types, in which a strong electrostatic field is formed by applying a voltage to a grid-like electrode provided inside the reactor. .
Although practically used as a neutron source by nuclear fusion, the fusion reaction rate (η _f ) is said to be low.

<Muon catalytic fusion>
“Muon-catalyzed nuclear fusion” is a method in which a nuclear reaction of deuterium (D) and tritium (T) is caused to approach to each other by giving a large mass of negative muons to DT molecules.
It takes 4 GeV to make a muon and 17.6 MeV of energy is obtained in one DT reaction, so if one muon performs more than 250 fusions, a breakeven is achieved, but at present it is 150 times. It is about.
Deuterium (D) and tritium (T) are used as fuels and converted into DT molecules, cooled to 5 to 30 K °, and confined in a furnace at 10 atm.
If the break-even has been achieved, the high-energy helium 4 (4 ^He) is generated by nuclear fusion, collide with the surrounding fuel gas, it means that raising the temperature of the fuel gas that is cryogenically cooled, Initial conditions may not be maintained.

<Cold fusion>
Although transmutation was confirmed to have occurred, no nuclear fusion phenomenon has been observed, and the mechanism has not been elucidated.
Recently, research has been promoted by changing the name to "agglutination-type fusion".
Even if nuclear fusion can be realized, the reaction is a reaction in a solid and the reaction speed is limited, so the output is considered to be limited.

<Charged particle beam collision type fusion>
In this method, charged particles are accelerated and collided by a particle accelerator (62) used in research on atomic nuclei and elementary particles to generate nuclear fusion.
Although nuclear fusion occurs without doubt as theoretically, there is a limit to increasing the fusion reaction rate (η _f ), and the accelerated fuel particles are wasted. (Patent Documents 1 and 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 small as several pA or less. It has been limited to academic research with low rates (η _f ).
Since there is no particle accelerator (62) having good acceleration efficiency (η _a ) that can be used for power fusion, the charged particle beam collision-type fusion (50) obtains “output energy larger than input energy. It cannot be expected. "(Non-Patent Document 1), and no research has been conducted.

Patent application 2015-000007 charged particle beam collision type fusion reactor Japanese Patent Application No. 2006-179051 Charged particle beam asymmetric collision type fusion Patent 4,865,934 (WO2011 / 136168) Charged particle accelerator and charged particle acceleration method Patent 2015-207517 Charged particle accelerator Patent application No. 2011-075452 Metal capillary manufacturing apparatus, metal capillary manufacturing method and metal capillary, and ion beam irradiation apparatus equipped with metal capillary Patent No. 4802340 (WO 2006/008840) Spherical aberration correcting electrostatic lens, input lens, electron spectroscope, photoelectron microscope, and measurement system

"Numerical calculation of fusion plasma" http: // repository. kulib. kyoto-u. ac. jp / dsspace / bitstream / 2433/83392/1 / 0832-04.pdf Japan Atomic Energy Research Institute Direct energy conversion jspf1995_06-516 Plasma Fusion Society Outline of dispersed charged particle accelerator http: // www. emcube. co. jp / acceleratorsummary. html JENDL-4.0 Universal 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 Serial Nuclear Fusion Reactor Production and chemistry of fusion reactor fuel tritium Japan Atomic Energy Research Institute Cutting-edge research and development of solid tritium breeding material Plasma Fusion Society

<Problems of the plasma method>
No fusion method using plasma has been observed in any of the fusion methods, and it cannot be said that the possibility of realization is high.
Even if the fusion is successfully generated, there is a problem that the fusion-produced charged particles (49c) are mixed with the plasma (fuel particles), and the protons (p), which are the final fusion-produced particles (49f), are generated from the plasma. And helium 4 ( ⁴ He) cannot be separated immediately.
Since it is a fusion-produced charged particle (49c) and contains tritium (T) as a fusion fuel, there is always a danger of leakage even when a part of plasma is taken out and subjected to separation treatment.

D-3 ^{the He} reaction is said to be safe fusion reactions, since the deuterium (D) Helium 3 (3 ^He) are mixed, would involve the reaction such as D-D reaction Unfortunately, the plasma method cannot be used for safe 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 is a first place because helium 3 (3 ^He) on the ground there is little, the reality of the fusion reactor for power utilizing this reaction alone can not.

The kinetic energy (K) of the fusion-produced charged particles (49c) flying isotropically in all directions repeatedly collide with other particles in the plasma, resulting in disordered thermal energy (Q). Therefore, direct power conversion was difficult.
There is also a concept (Non-Patent Document 2) in which high-temperature plasma is separated into electrons and charged particles by electromagnetic force, and velocity modulation is performed to obtain electric energy (E) by direct power conversion. Is required, the efficiency (η) is reduced, and the danger of leakage of tritium (T) is attached.
As for tritium (T), a method of separating the tritium (T) to the outside, returning it to a gas, and separating it by a chemical treatment, or a method of separating the charged particles in a state of charged particles by a difference in mass-to-charge ratio (m / z) can be considered.
Although it is considered that proton (p) and tritium (T) can be separated, deuterium (D) and helium 4 ( ⁴ He) have almost the same mass-to-charge ratio (m / z). Difficult to separate by state.

<Problems of charged particle beam collision type fusion>
The charged particle beam collision type fusion is a method of generating fusion by accelerating and colliding charged particles with two sets of particle accelerators, so fusion can be generated without doubt as theoretically. The acceleration efficiency (η _a ) of the accelerator was as low as 5% or less, and the collision rate (η _f ) of the particles was low, so that many particles were wasted, and it was considered that the particles could not reach break even.

  The purpose of this application is to first minimize the effects of neutrons (n) and tritium (T) from the nuclear fusion reaction that can be used with substances existing on the earth, and how to build a safe fusion reactor Is to be able to do it.

The fusion reaction rate (η _f ) is obtained from the particle density (ρ) and the fusion reaction cross section (σ).
The fusion reaction cross section (σ) changes depending on the speed at which particles collide, and a velocity (expressed in kinetic energy (K)) and a fusion reaction cross section (σ) appropriate for generating a fusion reaction are as follows. 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; at 400 keV, σ ≒ 1 barn
³ He- ³ He reaction; at 1 MeV, σ ≒ 0.01 barn
Note that 1 barn is 10 ⁻²⁴ cm ² .

<DD reaction>
When deuterium (D) is collided at 0.5-1.4 MeV,
Two reaction D + D → T + p and ³ the He + n occurs at a ratio of 50%.
You cannot choose either reaction.
FIG. 1 illustrates a set of DD fusion reactions,
(A) A deuterium (D) composed of a proton (p) and a neutron (n) collides at an energy of 500 keV to fuse,
(B) As an unstable helium nucleus containing the energy (U) of the mass defect,
(C) release protons (p) to tritium (T), or
And (d) changes in the neutron helium ³ by emitting (n) (3 He).

Since the energy (U) generated by the mass defect is distributed 1: 3 in inverse proportion to the mass of the particle, 1 MeV for tritium (T), 3 MeV for proton (p), and helium 3 ( ³ He). 0.82 MeV and 2.45 MeV to the neutrons (n), and come out in the form of kinetic energy (K) of particles that fly in opposite directions. (The direction of each flight axis is undefined, and the particles fly isotropically in the entire fusion-producing particle group.)
The kinetic energy (K) possessed by the particles can be converted to electrical energy (E) by temporarily converting to thermal energy (Q) and then generating power from heat.
Since the flow of charged particles (particles other than neutrons) is equivalent to an electric current, the kinetic energy (K) of the charged particles can be directly converted to electric energy (E) by utilizing the electromagnetic induction.
Neutrons (n) are dangerous particles, but can be shielded from leaking out of the furnace. (Proven in fission reactors, can be decelerated and absorbed by neutron moderator (10).)

Next, since tritium (T) is a dangerous substance, how to make it harmless is required.
In the case of a 200 MW nuclear fusion power reactor, tritium (T) of 11 kg or more is generated annually, and therefore, it is extremely dangerous to accumulate it.
It is desirable that the generated tritium (T) be separated and recovered instantaneously and be eliminated by the DT reaction described below.

<DT reaction>
By reaction of the tritium (T) is a deuterium (D) collide at ^{100keV D + T → 4 He +} n, 17.59MeV kinetic energy (K) is obtained.
FIG. 2 illustrates a set of DT fusion reactions,
(A) Tritium (T) and deuterium (D) collide with a kinetic energy (K) of 0.1 MeV, and nuclear fusion occurs.
(B) As an unstable helium nucleus containing the energy (U) of the mass defect,
(C) changes in the neutron and emits (n) 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 is distributed to helium 4 ( ⁴ He), and 14 MeV is distributed to the neutron (n). It comes out in the form of the kinetic energy (K) of a particle that vigorously jumps in a direction.
Helium ^{4 (4} He) is a charged particle capable of directly power conversion.
If tritium (T) generated by the DD reaction can be eliminated within 1 millisecond, the calculation can be such that the instantaneous abundance can be reduced to 1 μg or less.
11,540 / (365 × 24 × 3600 × 1000) = 0.000000036 [g]

<D-3He reaction>
When helium 3 ( ³ He) and deuterium (D) collide at 400 keV,
^{D + 3 He → 4 He +} p reaction by 18.45MeV energy (U) is obtained.
Since the neutrons (n) and tritium (T) are not contained in the fusion-producing particles, a safe fusion reaction is performed.
The plasma method in which deuterium (D) and tritium (T) are mixed is a nuclear fusion reaction that cannot be used as a safe nuclear fusion reaction.

3, D-3 is obtained by illustrating the ^He fusion reactions, occur readily reacted than the D-D reactions,
(A) Collision with energy of 400 keV,
(B) As an unstable lithium nucleus containing the energy (U) of the mass defect,
(C) to release protons (p) changes to a 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, and 3.7 MeV is distributed to helium 4 ( ⁴ He), and 14.8 MeV is distributed to the proton (p). Each comes out in the form of kinetic energy (K) that jumps out in the opposite direction.
Helium 4 (4 ^He), proton (p) is a charged particle capable of both direct power converter, at the same time D-3 ^{the He} reaction, if it is safe fusion reaction that does not contain the radioactive materials, direct power converter Therefore, it has an excellent feature that a small amount of heat is generated and a lightweight furnace can be configured.

First, the DD reaction is performed, then the DT reaction is performed, and the elimination of tritium (T) is performed. By linking the nuclear fusion reaction, helium 3 ( ³ He ), And helium 3 ( ³ He) can be used immediately or stored as a safe fusion fuel.
Will calculate capable of producing annual 11kg or more helium ³ (3 the He) at power reactor of 200 MW, it can be the fuel of the ^D-3 the He reactor that can be used as an engine of the moving object (simple furnace).
^{Although the 3} He- ³ He reaction can also be used as a safe fusion reaction, it is more realistic to use the D- ³ He reaction because the fusion reaction cross section (σ) is small.

Factors to consider when deciding on a safe fusion reactor are as follows.
-A system that can use nuclear fusion fuels that are abundant on the earth.
-A system that reliably generates fusion without wasting fusion fuel.
-Fusion fuel particles and fusion-produced charged particles (49c) can be easily separated and do not mix.
-To be able to immediately eliminate tritium (T), a dangerous radioactive substance.
-A method capable of directly converting kinetic energy (K) of charged particles into electric energy (E).
It can be concluded that fusion reactors using plasma have not yet produced fusion, and cannot be adopted because fusion fuel particles and fusion product particles are mixed.

Charged particle beam collision-type fusion is a method that is known to reliably generate fusion, but since it has been used only for research so far, it can be configured for power. To consider.
In the DD reaction, the collision requires 500 keV, and kinetic energies (K) of 3.27 MeV and 4.03 MeV are obtained. However, when the efficiency of the particle accelerator (η _a ) is 5% or less, break even cannot be achieved.
The acceleration efficiency (η _a ) of the recently developed distributed accelerators (Patent Literature 3, Patent Literature 4, Non-Patent Literature 3) is 60%, so that a break even can be achieved.
As a result of the study, we will select “Fusion charged particle beam collision type fusion that can separate fusion fuel particles and fusion generated charged particles” as the fusion reactor method.

<Combined furnace configuration>
An example of configuring a 200 MW power generation furnace will be described more specifically.
Nuclear fusion is generated by using the deuterium (D) as the first fuel by the "tritium annihilation cooperating reactor (50c)" which combines the DD reactor and the DT reactor shown in FIG.
Since neutrons (n) are generated, the reactor is covered with a neutron moderator (10) to shield the neutrons (n), convert its kinetic energy (K) into thermal energy (Q), and further generate thermal power. To obtain electrical energy (E).
On the other hand, electric power is directly converted by the fusion-produced charged particles (49c) to obtain electric energy (E).
Tritium (T) is separated from the decelerated fusion-produced charged particles (49c) and immediately sent to a DT reactor to be extinguished.
It is also possible to use a combined furnace having a configuration in which D particles and T particles collide alternately or simultaneously with one charged particle bunch of deuterium (D).
A configuration method in which a charged particle beam is generated by a pair of charged particle beam generators (60) and the charged particle beam is supplied to a plurality of fusion reactors (50) is also conceivable.

The electrical output of the "tritium disappearance cooperation furnace (50c)", as shown in Table 2, in the D-D reactions, fusion generates charged particles ^{(49c, T, p, 3} He) of having kinetic energy (K) If 85% can be directly converted into electric power, 48.1 MW of electric energy (E) can be obtained.
The kinetic energy (K) of the neutron (n) is converted into thermal energy (Q) by irradiating the neutron moderator (10) with the energy (Q) of the charged particles that cannot be converted to electric power and become heat. , 60% of thermal efficiency (η _Q ), 22.2 MW of electric energy (E) can be obtained, and a total of 70.3 MW can be obtained.
Table 2 Required acceleration power and electric output of "Tritium annihilation cooperative reactor"

The D-T reaction, when 85% of the kinetic energy (K) of a charged particle ⁽⁴ the He) can be directly power conversion 34.9MW of electrical energy (E) is obtained. All the energy of the neutrons (n) is converted to thermal energy (Q) through the neutron moderator (10), and the energy (Q) of the charged particles which cannot be converted to electric power and becomes heat is reduced by 60%. By performing thermal power generation with thermal efficiency (η _Q ), electric energy (E) of 102.2 MW can be obtained, so that a total of 137.1 MW can be obtained.
The kinetic energy (K, considering only high-speed fuel particles; the same applies hereinafter) required for collision of the fuel particles of the DD reaction and the DT reaction is 12.8 MW, and the acceleration efficiency (η _a ) is 60%. , 21.4 MW of electric energy (E) is required, whereas the obtained electric energy (E) is a total of 207.3 MW of 82.9 MW of direct power conversion and 124.4 MW of thermal power generation. Therefore, the “tritium annihilation cooperative furnace (50c)” can obtain a difference of 185.9 MW of electric energy (E).

<Structure of simple furnace>
The ^D-3 the He reactor shown in FIG. 5, may be configured with deuterium (D) Helium ^{3 (3} He) which allow movement to generate electricity as fuel "simple furnace (50s)" a.
D-3 ^{the He} reaction, since neutrons (n) does not occur, because there is no need to perform shielding, furnace is lightweight, allowing direct power converter because it is all fusion product particles charged particles, thermal Less occurrence.

Table 3 Required acceleration power and electric output of "simple furnace" The electric output of "simple furnace (50s)" is 182.9 MW of electric energy (85% of the kinetic energy (K) of charged particles can be directly converted into electric power. E) is obtained. If thermal power is generated at a thermal efficiency (η _Q ) of 60% from thermal energy (Q) that could not be directly converted to electric power, electric energy (E) of 19.4 MW can be obtained, so that a total of 202.3 MW can be obtained. can get.
The kinetic energy (K) required for the collision of the D- ³ He reaction is 4.7 MW, and when the acceleration efficiency (η _a ) is 60%, 7.8 MW of electric energy (E) is required. The furnace (50s) "is a calculation that can obtain an electric energy (E) of 194.5 MW, so that the electric energy (E) equivalent to the above-mentioned" tritium annihilation cooperative furnace (50c) "can be obtained. Can be.

<Beam collision>
A method of colliding a charged particle beam will be described.
In the nuclear fusion reaction, the charged particle generated by ionizing the fusion fuel gas by the charged particle generator (61) is accelerated by Coulomb force to bunch a pulse-like charged particle beam (62), a charged particle A fusion reactor vessel (58) using two sets of a charged particle beam generator (60) composed of an electron lens (63) for converging the beam and a deflector (64) for changing the flight direction of the charged particle beam. To cause a nuclear fusion reaction.

At the center of the fusion vessel (58), the charged particle beam is converged and deflected to a diameter of 1 to 2 μm and a length of 10 cm, and the fusion reaction cross-sectional area (σ) determined by the combination of the fusion fuels increases (at the time of collision). at a rate resulting kinetic energy by nuclear fusion (K) is increased relative to the kinetic energy (K) required, the ^D-3 the He reaction, collide with 400keV and forth.).
As the collision progresses, the fusion fuel particles of both charged particle bunches decrease, and the collision rate of the particles decreases in the latter half of the charged particle bunch.
By increasing the number of low-speed particles and increasing the speed of the other particles, it is possible to prevent a reduction in the collision rate in the latter half of the charged particle bunch and reduce the waste of electric energy (E) required for acceleration.

Assuming that the length of the charged particle beam is about 10 cm, the length of the nuclear fusion reaction region (52) is also about 10 cm at the maximum.
When the length is shortened, a large amount of charged particles are ejected instantaneously, so that the electron lens (63), the deflector (64) and the like are burdened.
If the length of the charged particle beam is set to 10 cm or more, the flying width of the flying fusion-produced charged particles (49c) also increases, and there is a possibility that separation of nuclides becomes insufficient. In the simple furnace (50s), there is no need to perform separation for each nuclide, so there is no such limitation.

<Particle accelerator>
Conventional accelerators use a high-Q cavity to introduce a high-power high-frequency wave into the accelerating cavity and form an accelerating electric field. The high-frequency cavity is also applied to a cavity without charged particles. Therefore, the loss is large and the acceleration efficiency (η _a ) is as low as 5% or less.
The dispersion type particle accelerator (62) is a method in which an accelerating voltage is sequentially applied only to the accelerating electrode near the charged particles as the charged particles progress, and therefore, the acceleration efficiency (η _a ) is as high as 60%. is there. (Patent Documents 3 and 4, Non-Patent Document 3)

The charged particles ejected from the particle accelerator (62) compress in the axial direction by increasing the speed of the particles behind the head.
When a flat particle accelerator (62) is used, the charged particle bunches compressed in the axial direction form charged particle bunches arranged in a row in a horizontal direction with respect to the traveling direction. 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 a charged particle bunch aligned in the traveling direction can be formed.

Inside the particle accelerator (62), when a part of the charged particle beam comes into contact with an electrode or a metal part of the accelerator, an accident may occur that the metal is melted.
A tough insulating container such as ceramic is provided between the charged particle passage and the electrode to prevent accidents.
The scattered charged particles come into contact with the inside of the insulating container to cause charging, which affects the trajectory of the charged particle beam. Therefore, it is necessary to remove the charging.
For this reason, after imparting appropriate conductivity, or after emitting charged particles, an acceleration operation is performed in the absence of charged particles, and charge is removed 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 large aberration, and is mainly used for a particle accelerator and an ion transfer path. Internally, it is incorporated as a structure of an accelerating electrode in order to maintain a beam so that the charged particle bunch does not disperse.
In the charged particle beam collision-type fusion reactor (50), a high-speed charged particle beam and a low-speed charged particle beam are emitted from the same direction. After the emission of the particle beam (after several microseconds), the magnetic field intensity is changed to the high-speed charged particle beam.

<Capillary>
The capillary (63c) converges the charged particles by using a tapered tube structure made of a tough insulator such as ceramic and one of which is thinned.
The charged particles incident on the inner wall surface of the capillary (63c) at a small angle are totally reflected and the charged particles are squeezed according to the gradually narrowing inner diameter of the tube. (63m) converges on a different principle.
Two or more capillaries (63c) can be arranged side by side in the same direction.

Even after leaving the tip of the capillary (63c), the charged particles try to go straight due to the inertia of each particle, so that the charged particle beam can be narrowly converged at a certain distance.
An electrode is provided outside the capillary (63c), a pulse voltage is applied to prevent charged particles from remaining inside the capillary (63c), and a pulse voltage is applied with no load to perform the removal operation.
The convergence of the charged particles by the capillary (63c) is regarded as a guiding effect by the charged particles on the inner surface of the insulator capillary (63c) such as a single crystal or polycrystalline ceramic. It has been confirmed that charged particles can be converged 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).
The flying direction of the charged particle beam is adjusted by the applied voltage or current using two sets of orthogonal deflectors (64).
Since the high-speed charged particle beam and the low-speed charged particle beam are emitted from the same direction, the low-speed charged particle beam is emitted using the electric field type deflector (64e) in common (for several microseconds). Later), the deflection intensity is changed to match the high-speed charged particle beam.
Although the positions at which the fast charged particles and the slow charged particles are fired are slightly different, in order to maintain a high fusion reaction rate (η _f ), the fast charged particles must penetrate the entire slow charged particle bunch. The entire particle bunch needs to collide.
Therefore, by changing the voltage while the slow charged particles are passing through the deflector (64), the inclination of the charged particle bunch with respect to the traveling direction is changed as shown in FIG. At, the beam is deflected so as to face 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, the firing positions of the respective particles are different. Cannot collide.
The charged particle bunch is sequentially fired toward the intermediate position between the charged particle launch position and the fusion reaction point (51), and directed toward the fusion reaction point (51) by the deflector (64) provided at the intermediate position. All charged particle bunches follow the same orbit and collide at the fusion reaction point (51).

<Flying of fusion production particles in DD reaction>
FIG. 6 shows the flying state of the fuel particles of the DD reaction and the fusion production particles.
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 about 1 μm and a length of about 10 cm. The charged particle bunch of deuterium (D) collides at a relative velocity of 0.5 MeV (6,900 km / s),
As shown in FIG. 6 (b), fusion generates particles at a following speed while flying towards (p, n, T, 3 He) equal, fusion reaction proceeds.
Proton (p): 24,000 km / s
Neutron (n): 21,600 km / s
Tritium (T): 8,000 km / s
Helium ^{3 (3 He): 7,200km /} s

As shown in FIG. 6 (c), the fusion-produced particles (p, n, T, ³ He) generated by the fusion exit outside the fuel particle beam having a diameter of 2 μm in a very short time. Fly without colliding or mixing with particles.
As shown by concentric circles in FIG. 6D, the fusion-producing particles (p, n, T, ³ He) flying isotropically spread in a spherical shell shape.
Since one of the fuel particles has a downward velocity of 0.5 MeV in the figure, the center of the fusion-producing particles spreading in a spherical shell travels downward at a speed of 3,450 km / s.
The flight speed of the fusion-producing particles (p, n, T, ³ He) group traveling upward in the figure decreases by 3,450 km / s at the maximum.
A maximum of 3,450 km / s is added to the flight speed of the fusion-producing particles (p, n, T, ³ He) group traveling downward in the figure.

As shown in FIG. 6 (e), the charged particles are separated into respective groups of charged particles in the order of p, n, T, and ³ He in order from the fusion-producing particles having the highest speed, and sequentially reach the periphery of the furnace. (Because neutrons n are not directly subjected to power conversion, they are not shown in FIG. 6E.)
Since the probability that high-velocity particles collide with low-velocity particles from the rear is extremely small, the fusion-produced charged particles (49c) are sufficiently separated at the periphery of the furnace (5 m or more from the fusion reaction point 51). .

<High-speed particle collision order>
The collision order when the DD reaction and the DT reaction are performed simultaneously will be examined.
(1) When high-speed D particles and high-speed T particles collide at the same time or high-speed D particles collide first, before colliding with low-speed D particles, high-speed D particles (500 keV) and T particles (100 keV) Collides at a relative velocity of 400 keV, and the fusion reaction cross section (σ) of the DT reaction is 0.8 barns, so that a maximum of about 30% of the D particles disappear.
Since the T particles are reduced, the DT response of the next cycle is also reduced, reducing the output by up to about 30%.
(2) When one of the high-speed particles collides from different directions The collision mode of the particles becomes more ideal, but the ion recovery path (68c) for the unreacted fuel particles (49n) is provided at two places. This necessitates a complicated furnace configuration and exposes the electron lens (63) and the like to the unreacted fuel particles (49n).
(3) In order to avoid collision of high-speed particles, high-speed T particles collide before high-speed D particles.
Since the density of the low-speed D particles is partially reduced by the DT reaction, the fusion reaction rate (η _f ) when the high-speed D particles collide varies, but the number of low-speed D particles increases. If it is large enough, the variation is small.
Further, since the high-speed unreacted fuel particles (49n, D) are circulated again as high-speed fuel particles, they work in the direction of suppressing output fluctuation.
From the above, (3) is adopted as the collision order.

FIG. 6F shows the flight of the fusion-produced charged particles (49c) when the DT reaction was generated immediately before the DD reaction (60 ns before the beginning of the DD reaction). ing.
The addition of D-T reaction, helium 4 to fusion product charged particles ^{(49c) (4 He, 3.52MeV} , 13,000km / s) is applied, but flies intersect the p particles of D-D reactions , The probability of collision with each other is low.
Although the difference in flight speed due to the asymmetric collision is included in each direction, in the periphery of the furnace (5 m or more from the fusion reaction point 51), p particles and ⁴ He particles are sufficiently different from other particles. Are separated.
Although the T particles and the ³ He particles can be separated, there is a large difference in flight speed depending on the flight direction (indicated by arrows ↓, ← →, ↑ in the figure) due to the asymmetrical collision, and FIG. As shown in f), when particles in a certain direction range (for example, a 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 furnace, the effect of asymmetry can be slightly reduced.

<Nuclear fusion reaction rate of the ^D- 3 He reaction>
Nuclear fusion reaction rate of the previous to ^"D- 3 He" reaction for (η _f), to consider.
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.
Reaction cross sections of ^D-3 the He reaction (sigma) is about 1barns ⁽¹⁰ -24 cm ^2).
When constructing a 200 MW power reactor, it is necessary that 7.28 × 10 ¹⁹ particles per second fuse.
Suppose you make 1000 collisions per second,
A high-speed charged particle bunch of helium 3 ( ³ He) narrowed to 10 cm in length and 1 μm in diameter,
When driving into a low-speed deuterium (D) charged particle bunch with a length of 10 cm, a diameter of 2 μm, and eight times the number of particles Collision error (δ) is acceptable up to ± 0.5 μm, and a low-speed deuterium (D) The particle density (ρ) of is
ρ = 7.28 × 10 ¹⁹ × 8 / (f × π × (1 × 10 ⁻⁴ ) ² × 10)
≒ 1.85 × 10 ²⁴ [cm ³ ]
It is. However, the particle density (ρ) of the low-speed charged particle bunch is 低速 because the shape of the charged particle bunch is not an ideal cylindrical shape, and the low-speed particles disappear due to collision and gradually decrease. As
ρ ≒ 0.927 × 10 ²⁴ [cm ³ ]
And

The mean free path (λe) where 1 / e particles collide is 1 × 10 ⁻²⁴ cm ^{2 because the} fusion reaction cross section (σ) is 1 × 10 ⁻²⁴ cm ² .
λe = 1 / (ρ · σ)
$ 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 high-speed fuel particles, almost disappears.

On the other hand, 87% or more of deuterium (D), which is a low-speed fuel particle, becomes unreacted fuel particles (49n). Therefore, by circulating and reusing unreacted fuel particles (49n), the utilization rate is reduced. improves.
When the low speed fuel particles (D) are circulated at 1 keV, the speed is 310 km / s. Therefore, when circulating at 1 ms, it is necessary to form a fuel particle circulation path (69) having a length of about 300 m. is there. (By reducing the velocity of the particles, it is possible to shorten the length of the fuel particle circulation path (69).)
Fast helium ³ (3 the He) unreacted fuel particles (49n) are safety issues is not, since it is very small, back to the gas by the scattering particles (49s) with an ion neutralizer (70), Collect in a gas cylinder (79) or the like.

<Fusion reaction rate>
Table 4, ^"D-3 the He" reaction is the calculation table of the "D-D" reaction and fusion reaction rate of the "D-T" reaction (η _f). (Indicated by unreacted rate (1-η _f ))
The fusion cycle (f) represents the number of fusions that occur in one second.
When the fusion cycle (f) is doubled to 2000 times per second, the density (ρ) of the slow particles is the same, and the number of slow particles ejected per second and the slow ion current ( _IL ) are both doubled. Becomes The number of fast particles and the fast ion current (I _H ) are the same, and the number of particles per bunch is halved.
Therefore, when the fusion cycle (f) is increased, the reduction of low-velocity particles due to collisions is reduced. Therefore, it can be expected that the fusion reaction rate (η _f ) can be maintained high. There is an upper limit because it is necessary to shorten the length of the circulation path (69).
Table 4 Nuclear fusion reaction rate calculation table

We study the fusion reaction rates (η _f ) of “DD” and “DT” reactions and “tritium annihilation cooperative reactor”.
In the DD reaction, since the fusion reaction cross section (σ) is as small as 0.13 barns (0.13 × 10 ⁻²⁴ cm ² ), the fusion reaction rate (η _f ) is about 50%. In the calculation table of No. 4, this problem is avoided by setting the number of particles (1.45 × 10 ²⁰ particles) requiring high-speed charged particles to twice (2.91 × 10 ²⁰ particles). .
The high-speed unreacted fuel particles (49n, D) circulate at a reduced speed, accelerate again, and are reused as high-speed fuel particles (D).
Of the fusion-produced charged particles (49c), tritium (T) is immediately separated and recovered, and is decelerated to 1 keV or less and sent to a DT reactor.

In the DT reaction, since the fusion reaction cross section (σ) is as large as 5 barns (5 × 10 ⁻²⁴ cm ² ), the fusion reaction rate (η _f ) becomes 99.99% or more. ) Is almost completely extinguished.
The effective length of the fusion reaction region (52) of the DT reaction (length at which 99% of the particles react) 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 necessary to separate and collect the unreacted particles (49n) and recycle to try to extinguish the tritium (T) again. It is necessary to have a proper configuration.

^{Although the 3} He- ³ He reaction was not listed in the calculation table of Table 4, the fusion reaction cross-sectional area (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 higher by one to two orders of magnitude.
When the density of the charged particle beam is high, the nuclear fusion reaction rate (η _f ) is significantly increased. Therefore, it is assumed that the beam density is converged to 0.1 μm to 0.3 μm to increase the beam density by 10 to 100 times. .
Since the neutron (n) generation rate can be considered to be the product of the heteroatom mixing rate contained in the fuel particles, if the D particle mixing rate is 10 ⁻⁹ , the neutron (n) generation rate is 10%. ^It has an excellent feature that it is extremely small at ^-18 .

<Direct power conversion>
A conductor is placed around the passage of the fusion-produced charged particles (49c), and electric energy (E) can be obtained by electromagnetic induction caused by the passage of the charged particles near the conductor.
The kinetic energy (K) of the charged particles is reduced by the amount converted to the electric energy (E), and the charged particles can be decelerated.
Neutrons (n) have no charge and are not directly subject to power conversion.

The fusion-producing particles fly isotropically from the fusion reaction region (52) headed by the fusion reaction point (51) toward the periphery.
In order to directly convert the kinetic energy (K) of the fusion-produced charged particles (49c) into electric power, it is necessary to arrange the regenerative moderator (67E) without a gap so as to surround the fusion reaction region (52).
The fusion-produced charged particles (49c) spreading from the fusion reaction region (52) toward the periphery are shared and converged for each surface of the polyhedron (32), and then guided to the regenerative speed reducer (67E).
FIG. 7C illustrates a polyhedron (32) as an example of a polyhedron (32). However, a polyhedron having a different number of faces, a cylindrical polyhedron, or the like may be used.

<Charged particle concentrator>
A method of realizing a take-in angle of ± 60 ° with an aspherical electrostatic field grid electrode (56e) having a concave shape has been proposed (Patent Document 6). Is as high as 800 keV to 14 MeV, the voltage required for convergence becomes extremely high, which is not practical.
The focal length also varies depending on the speed of charged particles and the mass-to-charge ratio (m / z).
FIG. 7A is an explanatory diagram of a charged particle convergent device (56) using an elliptical inner surface shape.
An ellipse has two focal points, and a particle emitted from one focal point is reflected at an arbitrary point (Λ) inside the ellipse, and its incident angle (θ ₁ ) and reflection angle (θ ₂ ) are equal. Have the property of converging to the other focus.
By arranging a plurality of charged particle concentrators (56) focusing on the fusion reaction point (51) in FIG. 7 (a), the charged particles can be omnidirectional regardless of the mass-to-charge ratio (m / z). The spread charged particles can be shared and converged.

In addition, since the charged particles collide with the inner wall surface of the charged particle converging device (56) at a shallow angle (θ ₁ <10 °), the charged particles collide with the inner wall surface at a right angle or an angle close to a right angle. Impact is greatly reduced.
On the side of the charged particle concentrator (56) near the fusion reaction point (51), the wall surfaces of the plurality of charged particle concentrators (56) overlap, so that the overlapping portion (the portion drawn by a broken line) The charged particle concentrator (56) is arranged for each of the constituent surfaces of the polyhedron (32) in a shape in which the wall surface is removed.

The shape of the charged particle concentrator (56) near the focal point far from the fusion reaction point (51) is gradually narrowed, and the charged particles are gradually focused.
The charged particle concentrator (56) is made of a tough insulator material such as ceramics, and on the outside thereof, electrodes (71, # 1 to 3) for removing static electricity are provided, and a positive high voltage is applied. Thus, the fusion-produced charged particles (49c) are prevented from being charged.
A high voltage is applied in a pulsed manner from the center side to the outer electrodes (71, # 1 to # 3) in order to remove charged charged particles.
When a current flows through the electrode (71) with the passage of the fusion-produced charged particles (49c), the kinetic energy (K) of the charged particles is reduced. Shape.

<Charged particle separator>
FIG. 7B is an explanatory diagram of a charged particle separator (68x) constituted by a fan-shaped magnetic field (68 m).
The kinetic energy (K) of the fusion-produced charged particles (49c) is converted into electric energy (E), and the particles are decelerated. Separate for each nuclide.
The charged particles of velocity (v), mass (m), and charge (q) in a magnetic field (B)
mv ² / r = qvB
Therefore, it rotates at a radius (r) with respect to a plane perpendicular to the magnetic flux (B), and within the electric field (E),
(1/2) mv ² = qE
Therefore, it accelerates in the direction of the electric field (E).

Table 5 Calculation table of mass-to-charge ratio (m / z) and radius of gyration Table 5 shows a calculation table of mass-to-charge ratio (m / z) and radius of gyration in a magnetic field of 1 Tesla.
Since the rotation radius of the magnetic field of tritium (T) and helium 3 (3 ^He) is different, it can be easily separated.
The tritium (T) and the proton (p) of the fusion-produced charged particles have the same radius of gyration in the magnetic field, so it is difficult to separate them by the magnetic field alone. Separating by the speed difference until reaching.
In the case of performing D-D reaction and D-T reactions simultaneously, helium 4 (4 ^He) is applied, come to fly to the second, but since it is almost the same as the rotation radius of tritium (T), separated Is difficult.
Helium ⁴ as (4 the He) can be separated at a flying speed difference, D-T reaction is generated immediately before the D-D reactions, first flight to come protons (p) and the second helium ⁴ (4 the He ), A negative deflection voltage is applied to the outer electrode (71, # 1), a positive deflection voltage is applied to the inner electrode (71, # 2), and the proton (p) and helium are directed outward. 4 ( ⁴ He) is accelerated and separated.

The regenerative speed reducer (67E, # 10) has a limited length that can be installed, and if the charged particles are excessively decelerated, the charged particles separated by the arrival time difference may be mixed. After that, separation by a charged particle separator (68x) is performed.
Particles having a smaller mass-to-charge ratio (m / z) have a larger deceleration effect, and therefore have a different radius of gyration in a magnetic field.
The fusion-produced charged particles (49c) separated by the arrival time difference are decelerated within a range where they do not mix again, so that the intensity 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 speed reducer (67E, # 11 to # 15), and convert the kinetic energy (K) remaining in the charged particles into electric energy (E).
In FIG. 7B, the arrangement of the regenerative reducers (67E, # 11 to # 15) is drawn radially, but the direction of the charged particles is changed by applying a magnetic deflection or using a gentle curved surface. Therefore, the regenerative speed reducers (67E, # 11 to # 15) can be arranged in parallel or to go around.

Since the charged particle separator (68x) and the regenerative moderator (56) can be a path through which the neutrons (n) leak to the outside, the central axis of the regenerative moderator (67E) is moved relative to the fusion reaction point (51). By detaching and attaching, and arranging the bent portion of 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 performing combined ^D-3 the He reaction, fast proton 14MeV to fusion product charged particles (49c) (p) is applied.
Since the speed of the scattered particles (49s) generated at the time of the collision of the charged particles or the charged particle beam having the static elimination is lower than that of the fusion-produced charged particles (49c), the innermost regenerative decelerator (67E, # 15) is used. Be guided.

The mass of the fusion-produced charged particles (49c) entering the charged particle separator (68x) is as small as 0.1 to 0.5 mg / bunch, but the speed is as high as 7,000 to 53,000 km / s. Therefore, the impact force at the time of collision reaches 10 kgf to 30 kgf.
The fusion period (f) is in the audio frequency range and emits acoustic noise due to the reaction of the deflection.
By shortening the repetition period of the fusion cycle (f), exceeding the audible frequency range and reducing the number of fusion-produced charged particles (49c) per bunch, reducing impact force and reducing acoustic noise. Can be.
In FIG. 7B, the particles are bent at an angle of 80 ° or more. However, particles can be separated with a smaller bending angle, and the impact force is obtained by deflecting the fusion-produced charged particles (49c) in the opposite direction after separation. , And acoustic noise can be reduced.

<Regenerative reducer>
It is made of a tough, cylindrical ceramic or the like that can withstand the irradiation of charged particles. Electrodes that are electromagnetically coupled to the charged particles are formed on the outside, and the kinetic energy (K) of the charged particles is directly converted to electric energy (E).

The ^D-3 the He reaction occurs at 1000 times per second rate, when nuclear fusion generated charged particles (49c) is 7.28 × ^{10 19} atoms / sec, protons charged particle stream of corresponds to a current of 11.7A Since the number of protons in one charged particle bunch is 7.28 × 10 ¹⁶ , this is equivalent to passing a positive charge of 0.0117 coulomb per second 1000 times at a speed of 53,000 km / s. (It passes 1 m in about 20 ns.)
If the charged particle stream of helium ^{4 (4} He), corresponds to a current of 23.3A, per 0.0233 Coulomb positive charge at a rate of 13,300km / s, equal to pass 1000 times.

When transmitting 200 MW of power, a DC current of 50 kV handles a current of 4 kA.
Of the total output 215MW of ^D-3 the He reactor, proton (p) is 172MW, helium ^{4 (4} He) has a 43MW kinetic energy (K).
In the case of regenerating using a 300-element regenerative speed reducer (67E) of 32 systems, each element carries about 56 kW of power, and each element handles 50 kV and a maximum current of 1.2 A as an average current.
Since the induced current induced in each element is a pulse (10 ns to 100 ns / 1 ms) having a large waveform ratio, it is necessary to use an element that can withstand the peak voltage and the peak current.

FIG. 8A shows a three-element electrostatic coupling type regenerative speed reducer (67e). An electrode (71) for performing electrostatic coupling is formed outside 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, the 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 are close to one and away from the other. Since a deceleration electric field of 50 kV is formed in the gap between the electrodes (71, # 1, # 2), the fusion charged particles (49c) are decelerated.
Extremely thin positive and negative pulse-like power is obtained at each electrode (71), and the output of the multi-stage electrode (71) is rectified, combined, and smoothed, thereby converting the DC electric energy (E). obtain.

FIG. 8B shows a magnetic coupling type regenerative speed reducer (67 m).
A magnetic material (72, including a case where the relative magnetic permeability (μ / μ ₀ ) is 1) is magnetically coupled to form an electrode (71) outside the cylindrical container.
Pulsed power is obtained at the electrode (71) magnetically coupled to the charged particle flow by electromagnetic induction, and the rectifiers (67d +, 67d-) conduct, rectify and smooth, thereby converting the DC electric energy (E). obtain.
The coupling to the charged particle bunch is determined by the magnetic permeability (μ) of the magnetic body (72), the length of the electrode (71), and the like. I do.
The actual regenerative speed reducer (67E) is in a coupling state in which an electrostatic coupling type (67e) and a magnetic coupling type (67m) are overlapped, and FIGS. 8A and 8B show this point. This is the layout of the rectifiers (67d +, 67d-) considered.

FIG. 8C shows an example in which a resistor (67R) is connected as a load of the regenerative speed reducer (67E).
At a position away from the regenerative speed reducer (67E), the resistor (67R) can generate heat and convert the 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 a regenerative speed reducer (67E) to convert the energy into thermal energy (Q) and integrate it into thermal power generation.
For the thermal power generation, the calculation is shown assuming that the thermal efficiency (η _Q ) is 60% (T _H = 750 ° C.). However, since the heat output can be increased to the heat-resistant temperature of the heat exchanger, the theoretical thermal efficiency of the Carnot cycle ( eta _Q) from a hot source _{(T H)} is 1300 ° K in the case when 77% can be expected thermal efficiency (eta _Q) is a high temperature source _{(T H)} is greater than 80% for 1800 ° K.
η _Q = 1− ( _TL / _TH )

When the charged particle bunch passes the electrode (71, # 1), some charged particles attract the charged particle at the tail of the bunch to the electrode (71, # 1) biased to −25 kV, so that some of the charged particles bunch off the electrode (71, # 1). 1) Residual or charged around.
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 particles of different nuclides. (Since the nuclides are not separated in the simple furnace (50s), mixing does not cause any problem.)
At the timing when the end of the charged particle bunch passes the electrodes (71, # 2) and the electrodes (71, # 2) change to −25 kV, the switch (67sw) of the electrodes (71, # 1) is turned on, and the electrodes (71, # 1) are turned on. By biasing (71, # 1) to +25 kV, the remaining or charged particles are repelled in the direction of the electrodes (71, # 2) to prevent mixing of nuclides of the charged particles.

The charged particle bunch decelerates each time it passes through each element of the regenerative speed reducer (67E) and loses kinetic energy (K). The amount of electric coupling and the amount of magnetic coupling are increased so that the output of each element is designed to be uniform.
The position of the regenerative speed reducer (67E, # 1 to # 32) is adjusted to shift the arrival time of the fusion-produced charged particles (49c) to avoid concentration of the regenerative power peak.
There is also a configuration method in which the same regenerative speed reducer (67E) is rotated many times.

<Neutron heat exchange room>
FIG. 9A is an explanatory diagram of the heat conversion chamber (67Q).
The heat conversion chamber (67Q) has an overall shape of a spherical shell and includes a plurality of neutron heat converters (67c) and neutron shields (67s), each of which is a polyhedron (32) as shown in FIG. 9 (c). And can be divided into regions corresponding to the respective surfaces.
The neutrons (n) generated by the fusion pass through the wall surface of the charged particle concentrator (56), and are converted into thermal energy by the neutron moderator (10) filled in the neutron heat converter (67c) and the neutron shielding chamber (67s). Convert to (Q), decelerate and absorb. The neutron moderator (10) uses water.

The neutron heat converter (67c) is located inside the neutron shielding chamber (67s), is filled with the pressurized neutron moderator (10), and decelerates 90% or more of the neutrons (n) generated by fusion. -Absorb and convert to thermal energy (Q). (Non-Patent Document 5)
The neutron heat converter (67c) has a neutron moderator (10) with a thickness of 50 cm or more, a through hole for securing a flow path for charged particles, and a shape capable of withstanding high pressure. And the neutron moderator (10) is circulated upward.

The neutron shield (67s) is filled with a neutron moderator (10) at normal pressure and slows down less than 5% of the neutrons (n) that have passed through the neutron heat converter (67c) to convert them into thermal energy (Q). At the same time, the neutrons (n) are absorbed and shielded.
The neutron shielding chamber (67s) is shaped so as to inject fuel particles and to increase the volume in the extension direction of the neutrons (n) because the neutrons (n) pass through the openings where the regenerative reducers (67E) are provided. .
The neutron shielding room (67s) can be removed for maintenance work, and the neutron shielding room (67s) is at an angle different from the neutron (n) radiation direction to reduce leakage between the adjacent neutron shielding room (67s). It has a multi-stage shape to fit.

Table 6 Neutron dose calculation table Table 6 is a neutron dose calculation table for the cooperative reactor (50c) and the simple reactor (50s).
In both cases, the annual exposure limit (1 mSv / year) of ordinary people is reached in 1 to 4 days.
In the cooperating reactor (50c) that performs the DD and DT reactions of 200 MW shown in FIG. 4, 14.6 × 10 ¹⁹ neutrons of 2.45 MeV and 14 MeV are generated, and at a point with a radius of 20 m, The effective dose of neutrons (n) transmitted through a 5 m thick layer of water is 0.277 mSv / day, taking into account the coefficients. (In this calculation table, neutrons are all 14 MeV. If the water thickness is 6 m, the annual exposure of ordinary people can be reduced, but the accommodation of charged particle separator (68x), regenerative decelerator (67E), etc. Since the thickness of the water in the portion is reduced, the length is set to 5 m.) The heat exchange chamber (67Q) has many penetrating portions, and neutrons (n) to be transmitted 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 that the annual exposure is below the allowable amount for ordinary people.
A light-weight neutron reflector (67b) is incorporated to reduce the neutron moderator (10), and a strong structural material such as low activation ferritic steel is required. These are included as neutron shields and reflectors. be able to.
Further, a part of the outer neutron shielding chamber (67s) having a small calorific value can be replaced with a light-weight solid neutron shielding body (67p) or the like.

A neutron multiplier made of beryllium (Be) or a substance containing 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) -2.5MeV
The doubled neutrons (n) react with the neutron moderator (10) in the neutron heat converter (67c) to generate deuterium (D) and tritium (T).
p + n → D + γ 1.67 MeV
D + n → T + γ
By regularly refining the neutron moderator (10), more deuterium (D) and tritium (T) as fusion fuels can be recovered.

<Neutron of simple reactor>
In simple furnace (50s) to perform only ^D-3 the He reaction 200MW shown in FIG. 5, but no occurrence of principle neutrons (n), D particles or T in ^3He fusion fuel (3 the He) When the particles are mixed, a nuclear fusion reaction that generates neutrons (n) occurs.
When the mixing rate is 10 ⁻¹² , when it is calculated that there is a shielding effect equivalent to that of a water layer having a thickness of 50 cm at a point with a radius of 10 m, the effective dose of neutron (n) is calculated as shown in Table 6. Is 0.813 mSv per day.

When neutron (n) reacts with helium 3 ( ³ He) as a fusion fuel, it changes to tritium (T).
^{3 He + n → T + p} + 0.764MeV
Since the amount of neutron emission from the simple reactor (50s) depends on the content of impurities in the fusion fuel, it is necessary to use a sufficiently purified fusion fuel and store it while avoiding neutron (n) irradiation. Immediately before the collision with helium 3 ( ³ He) as a fusion fuel, when it is bent by an ion bending device (68r) or the like, the different atomic nuclei (49s, D particles, T particles) due to the difference in mass-to-charge ratio (m / z). , Etc.) are important.
The effect of separating and removing foreign nuclei (49 s, D particles, T particles, etc.) is great. If the mixing ratio of foreign atoms is made 1/1000, the neutron moderator (10) has a neutron shielding room (50 cm thick). 67s) can be reduced.
In the case of a moving body, the load factor and operating time of the furnace can be taken into account.
There is also a method of providing a shielding plate made of a material having a large neutron shielding effect between an occupant and a fuel tank.

<Blanket>
The blanket used in the magnetic confinement fusion reactor uses lithium (Li), beryllium (Be), etc., which have a large neutron reaction cross section (σ _n ), to grow the fusion fuel tritium (T), The neutron (n) is shielded.
Lithium (Li) has an excellent shielding ability against neutrons (n), so that the thickness of the neutron moderator (10) can be reduced. (Non-Patent Document 6)
A reaction formula for absorbing neutrons (n) to produce a fusion fuel such as tritium (T) or doubling neutrons (n) is shown below.
⁶ Li + n → T + ⁴ He + 4.8 MeV
^{6 Li + n → n + D} + 4 He -1.5MeV
^{7 Li + n → n + T} + 4 He -2.5MeV
^{9 Be + n → 2 (4} He) + 2 (n) -2.5MeV
^{9 Be + 4 He → 12 C} + n
As a tritium breeding material, use of liquid lithium metal (Li, LiPb) and the like in addition to solid lithium compounds (Li ₂ O, Li ₂ TiO ₃ , LiH) and the like are also being studied.
By using beryllium (Be), a beryllium compound (Be ₁₂ Ti), or the like as the neutron doubling material and doubling the neutrons (n), the yield of tritium (T) can be increased.

(A) When liquid metal lithium (Li, LiPb) is used, a high-temperature liquid metal containing a radioactive substance circulated in a blanket is taken out to recover tritium (T). It's difficult to deal with.
(B) When a lithium compound containing oxygen (Ki ₂ O, LiOH, Li ₂ TiO ₃ ) is used, about 98% is recovered as tritium water (HTO molecule), so a separation method using a hydrophobic catalyst, etc. , A process of extracting only the tritium gas (13) is required.
(C) In the case of oxygen-free lithium compounds (LiH, Li ₃ N) and LTZO20 (Li ₂ TiO ₃ + 20% Li ₂ ZrO ₃ ), about 99% is recovered as tritium gas (13, HT molecules). Therefore, the separation treatment of tritium (T) is easy. (Non-Patent Documents 7 and 8)
When the tritium generation rate (η _t ), which is the ratio of the generated tritium (T) to the neutrons (n) generated in the DD and DT reactions, is 0.5, the output is about 1.6 times, .8, it is possible to configure a tritium multiplier (50t) of about 3.6 times.

By increasing the neutron multipliers of beryllium (Be) and lead (Pb), the neutron doubling effect by fast neutrons is also increased, and the local tritium (T) generation rate (η _t ) is 1.3 to 1. 4, and a tritium breeder reactor (50T) having an overall tritium generation rate (η _t ) of 1 or more can be configured.
When the production rate (η _t ) of tritium (T) exceeds 1, tritium (T) continues to increase, so that the operation can be continued only with the DT reactor. However, in order not to accumulate excess tritium (T), a neutron adjustment chamber (67v) with a thickness of 10 to 40 cm for injecting a neutron moderator (10) is provided inside the tritium breeding chamber (67T), and a blanket is provided. It is necessary to provide a structure capable of controlling the tritium generation rate (η _t ) itself, for example, by providing a mechanism for blocking the reaching neutron (n).
The DD reactor can be omitted, and the operation mode is such that the circulating tritium (T) is collected at the time of shutdown and stored as fuel for the next startup.
Since the fusion reaction rate (η _f ) of the DT reaction is large, the particle density (ρ) of deuterium (D), which is a low-speed fuel particle, can be reduced, and the demand for the particle accelerator (62) is also high. Can be lowered.
Furthermore, particles flying in D-T reactions, neutrons (n) and helium ^{4 (4} He) charged particle separator because only (68X) is not necessary.
By adding a resistor (67R) to the regenerative speed reducer (67E), the heat conversion type configuration is easy.

FIG. 9 (b) shows the heat obtained by adding a tritium breeding chamber (67T) filled with a substance containing lithium (Li) and beryllium (Be) used in a blanket of a magnetic confinement fusion reactor to a cooperating reactor (50c). This is the configuration of the exchange room (67Q).
The tritium breeding chamber (67T) is filled with a lithium compound (LTZO20) as a tritium breeding material and beryllium (Be) as a neutron multiplier, and the upper and lower tritium breeding chambers (67T) are connected by a connection pipe (67j). ing.
To reflux around 1% such as hydrogen gas (11, 12) added helium 4 gas (24), the resulting particles upon exposure to neutrons (n) ^(D, T, 4 the He, C) recovered I do.
The thermal energy (Q) contained in the recovered high-temperature gas is recovered, power is generated by heat, and electric energy (E) is obtained.
The recovered circulating gas contains about 1% of a gas such as hydrogen (11, 12) and about 0.01% of a tritium gas (13) with respect to the helium 4 gas (24), and contains carbon (C) and these gases. Fine powder such as the compound and breeding material.
The gas such as hydrogen (11, 12, 13) is concentrated using a hydrogen separator (82a) using a palladium alloy membrane (an alloy in which Ag, Pt, Au, etc. are mixed in a small amount in 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 and other gases (11, 12, 13) and heats. There is also a method of concentrating a gas such as hydrogen by using a hydrogen separator (82b) that releases hydrogen.
The concentrated gas such as hydrogen is sent to the charged particle generator (61), ionized, and only tritium (T) is selected based on the mass-to-charge ratio (m / z). Allow fusion reaction.
It is also conceivable to liquefy the recovered gas and separate it using the difference in boiling point.

Since it takes time to recover the tritium (T) in the tritium breeding chamber (67T), it takes 20 minutes for the reflux gas to make one cycle. The amount of tritium (T) produced in 20 minutes exceeds 0.4 g.
This means that the instantaneous tritium (T) abundance exceeds one million times as compared with the cooperative furnace (50c) having no tritium breeding chamber (67T).
Although the price of lithium (Li) per unit mass is lower than that of deuterium (D), safety measures for the tritium multiplier (50t) and tritium breeder (50T) are extremely important.

<Shutdown of tritium multiplier>
The stop of the tritium intensifier (50 t, limited to those having a DD furnace) requires a time period for the recovery of tritium (T) in the tritium breeding chamber (67T) even after the DD reaction is completely stopped. Therefore, the annihilation operation (DT reaction) must be continued while circulating tritium (T), and the production of tritium (T) by neutrons (n) generated by the annihilation operation of tritium continues.
Although the circulating tritium (T) is designed to decrease with time, even if the production rate (η _t ) is 50%, it takes more than one hour for the tritium (T) production amount to decrease by a factor of ten. Therefore, it is necessary to run the tritium (T) for 6 hours or more.

When a plurality of tritium multipliers (50t) are operating simultaneously, a neutron (n) reaching the tritium breeding chamber (67T) when the neutron moderator (10) is injected is provided with a cavity with a thickness of 10 to 40cm. Is shut off without generating new tritium (T), the time required for stopping can be reduced.

<Scale of fusion reactor>
The simple furnace (50s) can also be configured as an aircraft or space shuttle engine.
The thrust for one large aircraft corresponds to approximately 200 MW.
The 200 MW cooperating furnace (50c) consumes 38.45 kg of deuterium (D) (192.5 kg of heavy water) annually, so the 200 MW cooperating furnace (50c) needs to meet the total power consumption of 1000 TWh in Japan. ) Requires 570-1000 units, and consumes 110 tons of heavy water per year. (If you do not want to use the ^D- 3 He reaction.)
When converted to natural water, it is over 730,000 tons, which is a huge amount of water.
If also used D-3 ^{the He} reaction, the consumption of heavy water is reduced to almost half and 65.9T, but is still substantial amount.

If simple furnace to use only ^D-3 the He reaction of 200MW of (50s), from consumes annually 7.69kg deuterium (D) ^3He (heavy water 38.45Kg) and 11.54kg (3 He) , if the annual 4.39t deuterium (D) (heavy water 22t) and helium of 6.58t ^{3 (3} He) is, it is possible to cover the total power consumption of Japan.
A tritium breeder reactor consisting solely of a DT reactor can operate using 7.69 kg of deuterium (D) and 26.9 kg of lithium (Li) as fuel per year.
Helium 3 ( ³ He) will be activated from the moon, etc. rather than constructing a large number of cooperating reactors (50c), multipliers (50t), and breeding reactors (50T) that are activated by neutrons (n) and handle dangerous tritium (T). procurement, and also from the point of view of protection of resources, I think that should build a simple furnace (50s) to use only safe D- 3 ^He reaction.

By giving up on plasma-based nuclear fusion, which does not progress slowly, nuclear fusion power generation can be realized at once.
Performs D-D reactions, then subjected to D-T reaction, producing helium ³ (3 the He), performs disappearance of tritium (T) "cooperation furnace (50c)", tritium breeder reactor with lithium blanket (50t, 50T) can provide a huge amount of energy.
D-3 performs ^He reaction "simple furnace (50s)" is equivalent to energy "cooperation furnace (50c)" (E, Q) can be obtained, because a fusion containing no radioactive substance, moving It can also be used as a body propulsion.

Behavior of fusion particles in DD reaction Behavior of fusion particles in DT reaction Behavior of nuclear fusion particles of D- ³ He reaction Tritium annihilation-linked charged particle beam collision type fusion reactor (DD, DT reactor) Simplified charged particle beam collision type fusion reactor (D-3 ^{the He} reactor) Flight of fusion-produced particles (a) to (e) DD reaction, (f) DD and DT reaction (A) charged particle concentrator, (b) charged particle separator, (c) polyhedron Regenerative reducer (a) Electrostatic coupling type, (b) Magnetic coupling type, (c) Resistor load type (A) Neutron heat conversion room, (b) Tritium breeding room Simplified charged particle beam collision type fusion reactor (Example 1) Thermal conversion type charged particle beam collision type fusion reactor (Example 2) (a) Longitudinal sectional view, (b) Transverse sectional view, (c) Nuclear fusion power generation device composed of a thermal conversion furnace Tritium annihilation-linked charged particle beam collision-type fusion reactor (Example 3) (A) ion flow bending device, (b) ion neutralizer (A) Circulation of neutron moderator in tritium annihilation cooperative reactor (Example 3), (b) Circulation of tritium in tritium multiplier (Example 4) Tritium circulation in tritium breeder reactor (Example 5)

<Example 1: Simple furnace>
FIG. 10 is a configuration diagram of the simplified (50 s) charged particle beam collision type fusion reactor (50) of the first embodiment.
As a charged particle collision method, one is a low-speed charged particle beam having a large number of 2 μm diameter particles of deuterium (D), which is easily available, and the other is a small number of 1 μm diameter particles of helium 3 ( ³ He). The system is configured to collide a high-speed charged particle beam to cause a fusion reaction of the charged particles without waste.
The low-speed charged particle beam generator (60, # 01) includes a charged particle generator (61, # 0), a particle accelerator (62, # 01, # 02), and an electron lens (63) for converging the charged particle beam. And a deflector (64) for adjusting the direction of the beam, and further include an ion recovery path (68c) and a regenerative decelerator (67E, # 00), an ion transfer path (68), and an ion flow bending device. (68r) constitutes a fuel particle circulation path (69, # 0).
The high-speed charged particle beam generator (60, # 11) includes a charged particle generator (61, # 1), a particle accelerator (62, # 11, # 12), and an electron lens (63) for converging the charged particle beam. , A deflector (64) for adjusting the direction of the beam, and a fuel particle circulation path (69, # 1) composed of an ion transfer path (68) and an ion flow bending unit (68r).

The deuterium gas (12) and the helium-3 gas (23), which are fusion fuels, are ionized by the charged particle generators (61, # 0, # 1) and the charged particles are accelerated by the particle accelerators (62, # 00, # 10). Accelerates to 0.1 keV to form a bunch of pulsed charged particle beams, and sends out to a fuel particle circulation path (69, # 0, # 1) comprising an ion transfer path (68) and an ion flow bending device (68r). In this configuration, final acceleration is performed by the particle accelerators (62, # 01, # 11).
A low-speed beam with a large number of particles is fired first, and then a high-speed particle beam is fired with a time difference.

The speed of the charged particle beam to be emitted is set to a relative speed (slow 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 the fusion fuel is increased. .
In the elongated fusion reaction region (52) headed by the fusion reaction point (51), the launch time and launch direction and the bunch tilt are adjusted so that the entire bunch collides.
Deuterium mixed in helium ^{3 (3} He) of the fuel (D), different nuclei such as tritium (T) (49s) are responsible for neutrons (n) occurs.
Since the ion stream bending device (68r) ejects particles of nuclides other than those to be transported at an angle different from the basic bending angle, it is possible to pass through the ion flow bending device (68r, # 11, # 12). Remove as many nuclei as possible (49s). (Rate of mixed nuclei: ^10-12 or less)
The separated foreign nucleus (49s) is given an electron from the electron generator (70e), returned to gas by the ion neutralizer (70, # 0), and collected in a gas cylinder (79, # 0).

The unreacted fuel particles (49n) that have passed without performing a nuclear 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 the regenerative deceleration is performed. Decelerating to 0.1 keV by the ionizer (67E, # 00) and passing through the fuel particle circulation path (69, # 0) constituted by the ion flow bending device (68r, # 04, # 05) and the ion transfer path (68). Then, the fuel is circulated to the low-speed particle accelerator (62, # 01), and the unreacted fuel particles (49n) are reused.
Although not shown, the ion flow bending device (68r, # 01, # 05) has a structure in which the charged particle flows from the regenerative decelerator (67E, # 00) and the particle accelerator (62, # 00) are combined. There is a need to.

Fusion product charged particles produced by nuclear fusion (49c, p, 4 ^He), since out of the fuel particle beam very short time the diameter 1μm and 2 [mu] m, the isotropic without colliding with the other fuel particles the flying fast p particle speeds, in the order of ⁴ He particles, and reaches the periphery of the fusion reactor.
Condensed by charged particle concentrators (56, # 1 to 32) arranged so as to surround and surround each face of the polyhedron (32), and regenerated by a regenerative reducer (67E, # 1 to 32) of 300 elements The electric energy (E) is obtained by directly converting the kinetic energy (K) of the charged particles into electric power.
The simplified (50 s) charged particle beam collision type fusion reactor (50) does not include dangerous substances such as tritium (T) in the fusion product particles, and therefore does not require a charged particle separator (68x). .
Fusion product charged particles (49c), all final fusion product particles from ^{(49f, p,} 4 the He) is an ion neutralizer (70, # 1-32) by electron generator electrons (70e) Give it back to gas and collect in gas cylinder (79, # 0). (Including mixed scattering particles, etc.)

Although the length of the particle accelerator (62) is generally several tens of meters or more, the lengths of the ion transfer path (68), the particle accelerator (62) and the regenerative decelerator (67E) in FIG. It is shortened for the sake of illustration.
The length of the ion transfer path (68) is a length that matches the nuclear fusion generation period (1 ms) in consideration of the transit time of the particle accelerator (62), the transfer speed of the charged particles in the ion transfer path (68), and the like. I have to.
The low-speed particle accelerators (62, # 01, # 02) and the high-speed particle accelerators (62, # 11, # 12) each 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 positions of the high-speed and low-speed charged particle beams and the amount of the particles, and stores data necessary for controlling the collision state and the like. Have acquired.
In addition, the container of the charged particle concentrator (56) is given a role of a vacuum container (55), and its surroundings are used as a heat removal chamber (67a) to circulate helium 4 gas (24) and recover heat.
The heat circulation mechanism and the heat generation mechanism are not shown in FIG.

<Stop procedure>
The shutdown of the simple (50 s) 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 is changed in deflection intensity of the ion flow bending device (68r, # 04) and sent to the ion neutralizer (70, # 0) to give electrons to neutralize the gas. (79, # 0) and shut down the furnace.

<Example 2: Heat conversion furnace>
FIG. 11 is an explanatory view of a heat conversion type (50h) charged particle beam collision fusion reactor (50) of the second embodiment.
As a collision type of charged particle, a simple furnace (50s) and similar, one of the charged particle beam slow often the number of particles diameter 2μm of readily available deuterium (D), the other is helium 3 (3 ^He) A high-speed charged particle beam having a small number of particles having a diameter of 1 μm is caused to collide, and the charged particles undergo a fusion reaction without waste.
FIG. 11 (a) is a longitudinal sectional view, and the whole shape is a truncated cone. FIG. 11 (b) is a transverse sectional view, and a charged particle concentrator forming a reflection surface based on a radially elliptical surface rotating to the right. (56, # 1 to 10) and an ion orbiting speed reducer (67l) formed of a single thread groove provided therearound.
The fusion-produced charged particles (49c) generated in the fusion reaction region (52) are reflected on one surface of the charged particle converger (56, # 1 to 10), and each charged particle bunch is provided around. It is guided to the ion circulation speed reducer (67l) and rotates rightward in FIG. 12 (b).
A charged particle rectifier (56 g, shown by a dashed line) is disposed inside the charged particle concentrator (56), and the charged particles flying in a direction close to the axis are guided to the ion circulation speed reducer (67l). (The charged particle rectifying plate (56g) does not exist in the heat exchange chamber (67Q).)

The bunch of the fusion-produced charged particles (49c) orbits along a thread-shaped groove provided on the inner surface of the ion orbital decelerator (67l).
A planar or mesh-shaped resistor (67R) is embedded in the wall surface of an ion orbiting speed reducer (67l) made of an insulating material, and an induced current caused by charged particles flowing in a pulse along the groove is applied to the resistor (67R). And generate heat.
Although not shown in the figure, an electrode may be embedded in the wall surface of the ion circulation speed reducer (67l), and a resistor (67R) may be placed at a remote position to generate heat.

The latter half of the ion orbital decelerator (67l) has a closed groove shape and is not shown in the figure, but is surrounded by a magnetic material to form a closed magnetic path, so that the charged particle flow and the resistor ( 67R) to enhance the magnetic coupling with the induced current flowing through.
The groove (closed groove) of the ion circulation speed reducer (67l) avoids the support structure of the ion recovery path (68c) (accommodation parts such as the ion flow bending device (68r, # 03) and the cooler (85)). It is formed as follows.
The ion flow bending device (68r, # 03) uses a magnetic field with a stronger magnetic field toward the outside, reflects charged particles (49n, 49c) in the same direction regardless of nuclide, and recovers them from the ion recovery channel (68c). The unreacted fuel particles (49n) are circulated to the low-speed particle accelerator (62, # 01).

Air or gas is sent to the heat exchange chamber (67Q), and heat exchange is performed through the wall surface.
A resistor (67R) is also embedded in the charged particle concentrator (56) and the charged particle rectifier (56g) to efficiently convert the kinetic energy (K) of the fusion-produced charged particles (49c) into thermal energy (Q). I do.
Although not shown in the figure, a regenerative speed reducer (67E) can be embedded in the wall surface of the ion orbital decelerator (67l) to extract electric energy (E) by direct power conversion. Power for driving can be covered.

FIG. 11 (c) shows a heat conversion type (50h) charged particle beam collision nuclear fusion reactor (50) including a fuel particle circulation path (69) composed of an ion transfer path (68) and an ion flow bending device (68r). Is shown.
The configuration of the low-speed fuel particle circulation path (69, # 0) is almost the same as that of the simple furnace (50s) in FIG. Circulate through the low-speed fuel particle circulation path (69, # 0) until the next high-speed fuel particle is fired and collides.
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).

The fusion-produced charged particles (49c) decelerated by the ion circulation decelerator (67l) are collected in the gas cylinder (79) via the ion transfer path (68) and the ion neutralizer (70).
Helium ³ remaining without disappearing (3 the He) or contaminating fusion product particles (49c), separated by kicker (68k), and, in the ion neutralizer (70) of deuterium (D) when stopping It is sent back to gas and collected in a gas cylinder (79).

The air or gas sucked in from the left side of FIG. 11A 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). And a nuclear fusion thermoelectric generator (81).
Fusion using helium 3 ( ³ He) does not generate neutrons (n) and does not generate tritium (T) in principle, so there is no need to separate the fusion-produced charged particles (49c).
The axial length of the bunch of charged particle beams is small, and
The heat conversion furnace (50h) has a remarkably small number of parts and has a simple furnace structure.

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

<Example 3: Cooperating furnace>
FIG. 12 is a configuration diagram of a charged particle beam collision-type fusion reactor (50) of a tritium annihilation cooperation type (50c, DD, DT reactor) of Example 3.
As the collision method of charged particles, one is a deuterium (D), which is easily available, and is a low-speed charged particle beam having a large number of particles having a diameter of 2 μm, and the other is a deuterium (D) and tritium (T). A high-speed charged particle beam having a small number of particles having a diameter of 1 μm is caused to collide with each other so that the charged particles undergo a nuclear fusion reaction without waste.
The low-speed charged particle beam generator (60, # 00) includes a charged particle generator (61, # 0), a particle accelerator (62, # 0, # 00), and an electron lens (63) for converging the charged particle beam. , And a deflector (64) for adjusting the direction of the beam, and further, an ion recovery path (68c) and a regenerative decelerator (67E, # 0), an ion transfer path (68), and an ion flow bending device. A fuel particle circulation path (69, # 00) constituted by (68r) is used, and deuterium (D), which is a low-speed unreacted fuel particle (49n), is reused.

A 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 converging a charged particle beam. , A deflector (64) for adjusting the beam direction, and a fuel particle circulation path (69, # 01) composed of an ion transfer path (68) and an ion flow bending unit (68r). Deuterium (D), which is an unreacted particle (49n), is reused.
The associated reactor (50c) uses deuterium (D), which is readily available, as the first fusion fuel for the low and high speed beams.
Another high-speed charged particle beam generator (60, # 1) includes a particle accelerator (62, # 11), an electron lens (63) for converging a charged particle beam, and a deflector (60) for adjusting the beam direction. 64), the tritium (T) generated by the DD reaction is separated and decelerated by a charged particle separator (68x) and a regenerative speed reducer (67E, # 14 to 324), and circulated as charged particles. ing.

The deuterium gas (12) is sent to the charged particle generator (61, # 0) to be ionized, sent to the particle accelerator (62, # 0), and includes an ion transfer path (68) and an ion flow bending device (68r). The fuel is sent to the fuel particle circulation path (69, # 00, # 01).
The length of the particle accelerator (62) is generally several tens of meters or more, but the ion transfer 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 nuclear fusion generation cycle, 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 for both low-speed and high-speed beams as an easily available fusion fuel.
The D-D reaction produces a tritium (T) and helium ^{3 (3} He), tritium (T) immediately extinguish by D-T reaction.

Helium 3 ( ³ He) is returned to gas as a safe fusion fuel and accumulated in a gas cylinder (79, # 3, 23) to be used as a fusion fuel for a simple reactor (50s).
Tritium disappearance cooperation furnace (50c, D-D, D -T reactor), by adding ^D-3 the He reactor, and configured to be used immediately transferred helium ³ (3 the He) in the form of charged particles You can also. (Emergency such as an earthquake only, helium ³ (3 He) is used as a fuel, continue to run switch to the ^D- 3 He reaction, etc..)

D-D reactor and D-T reactor, or in addition to D-3 ^{the He} reactor, it may be an independent fusion reactor, share fusion reactor vessel (58), D- A configuration in which D and DT reactions occur alternately may be employed. Further, a configuration may be employed in which a low-speed beam is shared and DD and DT reactions occur simultaneously, or DD and DT reactions alternately occur with respect to circulation of the low-speed beam.
Embodiment 3 of FIG. 12 is a configuration example in which the fusion reactor vessel (58) and the low-speed beam of the DD reactor and the DT reactor are shared.
The configuration is such that DD and DT reactions are generated simultaneously (high-speed T particles collide before high-speed D particles). Considering this, the number of particles is set larger than that shown in Table 4.

The particle accelerator (62, # 0) fires two charged particle bunches at a certain time difference at 1 keV.
A kicker (68k, # 0) that changes the path of charged particles by changing the electric or magnetic field,
One is sent to the fuel particle circulation path (69, # 00), formed as a charged particle bunch by the particle accelerator (62, # 00), and is launched as a 1 keV low-speed charged particle beam.
The other 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 collides at the fusion reaction point (51) Let it.

The velocity of the charged particle beam is determined by an appropriate relative velocity (kinetic energy (K) required for collision with respect to kinetic energy (K) required by the nuclear fusion reaction, where the fusion reaction cross section (σ) determined by the combination of the fusion fuel is large. ) Is increased, and the entire elongated shaped charged particle bunch is collided to generate a fusion reaction in the elongated fusion reaction region (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 flies to isotropic without colliding with the fuel particles at a rate shown in Table 5, from fast speed particles ^{n, p, n, 4 He} , in the order of ^T, 3 the He, fusion reactor vessel (58) Reach the periphery.

The charged particles (49c) generated by the fusion are converged by the charged particle concentrators (56, # 1 to 32) which are arranged so as to surround and surround each surface of the polyhedron 32, and a three-element regenerative decelerator (67E, According to # 1 to 32), a part of the kinetic energy (K) of the charged particles is directly converted into electric power to obtain electric energy (E).
Since the asymmetric collision is performed, in the case of the DD reaction, one of the fuel particles has a velocity of 0.5 MeV (6,919 km / s), so that the flying velocity of the fusion-producing particles is almost halved in the same direction. (Kinetic energy (K) of 250 keV) is applied. A difference occurs in the kinetic energy (K) of the fusion-produced charged particles (49c) between the upper side and the lower side of the furnace.

Next, the fusion-produced charged particles (49c) are separated by a charged particle separator (68x), and a regenerative decelerator (67E, p: 60 elements # 11 to 321; ⁴ He: 36) of 8 to 60 elements for each nuclide. element # 12~322, T: 20 element # ^13~323, 3 He: performing direct power conversion by 8 element # 14-324).
Of the final fusion product particles (49f), for ^p, 4 the He and ³ the He, ion neutralizer (70, # 1, # 2, # 4) by giving an electron gas (11,24,23) And collected 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 in which the fusion-produced charged particles (49c) are grouped for each nuclide and then neutralized by three ion neutralizers (70), but the ion transfer path (68) and the ion flow bending device (68r) Are required.)

Tritium (T) passes through the fusion fuel circulation path (69, # 1) composed of the dedicated ion transfer path (68) and the ion flow bending device (68r, # 11-13), and remains charged particles. Then, it is transported to the particle accelerator (62, # 11, T), accelerated to 100 keV, and fired so as to collide with the low-speed D particles just before the high-speed D particles collide.
FIG. 12 shows only one fusion fuel circulation path (69, # 1) dedicated to tritium (T), but the number of charged particle concentrators (56, # 1) equal to the number of faces of the polyhedron (32) 32), a large number of ion flow bending devices (68r) and an ion transfer path (68) are combined to be combined into one charged particle flow, and transported to the particle accelerator (62, # 11, T). .

The unreacted fuel particles (49n) that have passed through the fusion reaction region (52) without performing fusion, as shown in Table 4, have a low fusion reaction rate (η _f ) of D particles, so The particles are circulated and reused.
The unreacted fuel particles (49n) are recovered from the ion recovery path (68c) provided at the lower part of the fusion reactor vessel (58) and reused.
In addition to the fuel particle circulation path (69, # 00, # 01) for deuterium (D) constituted by the ion flow bending device (68r) and the ion transfer path (68), a charged particle generator (61, # 0) And deuterium (D) replenished from the particle accelerator (62, # 0) are synthesized,
The unreacted fuel particles (49n, D) of the low-speed beam are sent to the low-speed particle accelerator (62, # 00).
The unreacted fuel particles (49n, D) of the high-speed beam are decelerated by the regenerative speed reducer (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 first, but are reused and fired after the low-speed D particles, so that the fuel particle circulation path (69, # 01) ) Is made longer than the fuel particle circulation path (69, # 00) to 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) becomes too large, so that the charged particle generator ( 61, # 0, and # 1) are adjusted.

Although not shown in the figure, the amount, the arrival position, and the time of the charged particle beam are detected from the voltages, the voltage deviations, and the times generated in the plurality of annularly arranged electrodes in the ion collection path (68c). Equipped with a sensor, it acquires data necessary for grasping the collision state.
The charged particle concentrator (56) is given a role as a vacuum vessel (56), and circulates a helium 4 gas (24) to a heat removal chamber (67a) around the charged particle concentrator to cool and heat the equipment. .

<Ion flow bending device>
FIG. 13A shows an ion bending device (68r, # 03, # 08) and an ion neutralizer (70) constituted by two fan-shaped magnetic fields (68m, # 03, # 08) corresponding to FIG. FIG.
The ion flow bending device (68r) bends the flow of charged nuclide particles in an arbitrary direction using a sector-shaped magnetic field and electric field.
Table 7 is a calculation table of the radius of gyration in a magnetic field of 1 Tesla with respect to the velocity of the fuel particles.
The ion flow bending device (68r) bends the flow of charged nuclide particles by a fan-shaped magnetic field.
The bending angles which are the basic bending angles of the ion bending device (68r) shown in FIGS. 10 to 15 are all illustrated as 90 °, but this is due to the convenience of the plan view for explanation. The basic bending angle is designed according to the three-dimensional arrangement.
The nuclide particles and the particles having different velocities, which are not transported, are ejected at an angle different from the basic bending angle, so that the charged particle stream can be purified together.
Table 7 Calculation table of radius of gyration 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 bending device (68r, # 03) and sent to an ion transfer path (68, # 1).
Deuterium (D), which is a high-speed fuel particle, penetrates the ion flow bending device (68r, # 03) and is aimed at the ion flow bending device (68r, # 08) with a stronger fan-shaped magnetic field (68m). And sent to the ion transfer path (68, # 2).
Of the scattered particles (49s), the slower one goes toward the inside of the fan-shaped magnetic field (68m), and is guided to the ion neutralizer (70) via the scattered particle separator (68s) without a magnetic field. .
A negative voltage is applied to the grid electrode (73e, # 0) to induce scattering particles (49s).
The fusion-produced charged particles (49c) also enter the ion recovery path (68c), but penetrate the two fan-shaped magnetic fields (68m, # 03, # 08) due to their high speed, and enter the ion neutralizer (70). To reach.

The ion flow bending device (68r) and the ion neutralizing device (70) are made of an insulating material such as ceramic, and prevent an accident due to contact of charged particles with the electrode.
Although not shown in the drawing, an electrode (71) is provided on the outer surface of the insulating material, also on the pole face.
In a time zone where charged particles do not enter, a pulsed high voltage is applied to these electrodes (71) to remove charged charged particles.

<Ion neutralization>
The lower part of FIG. 13A is an ion neutralizer (70, # 0).
The potential of the grid electrode (73e, # 1) is kept at a more negative potential than the grid electrode (73e, # 0), and the scattering particles (49s) and the fusion-produced charged particles (49c) are guided to a nozzle with a narrowed tip. It is discharged, neutralized by a microwave discharge type electron generator (70e), and returned to gas.
The voltage of the grid electrode (73e, # 0, # 1) connected in series is divided by a high resistance and applied to the voltage dividing electrode 71e, and the voltage is applied between the grid electrodes (73e, # 0, # 1) toward the tip of the nozzle. An induced electric field is formed.
Since the speed varies depending on the nuclide, a method of instantly adjusting the voltage of the aspherical grid electrode (73e) at each arrival time of the particle so that each type of charged particle stably passes through the narrowed flow path may be used. is there.
The gas generated by the neutralization is sucked by a high vacuum pump (76h) such as a turbo molecular pump, and is pressurized by a multi-stage vacuum pump (76), not shown in the figure, to produce a gas cylinder (79, # 0). ).
Charged particles are ejected from a nozzle with a narrowed end into a circular container, and a gas that could not be sucked by a high vacuum pump (76h) is rotated to prevent a backflow of the neutralized gas.

In any of the ion flow bending devices (68r) shown in FIGS. 10 to 15, foreign nuclei (49s) mixed in charged particles intended for bending and occluded gas particles contained in a material facing the vacuum (00) of the furnace are separated. Although not shown in the figure, an ion neutralizer (70) is required for all ion flow bendrs (68r) because they are discharged only slightly.
The neutralization device (70, # 0) discharges the fusion-produced charged particles (49c) irradiated to the opening surface of the ion recovery path (68c).
These fusion-produced charged particles (49c), scattering particles, foreign nuclei, and scattering particles (49s) are collected in a gas cylinder (79, # 0).

FIG. 13B is an explanatory diagram of the ion neutralizer (70) connected to the regenerative speed reducer (67E).
An induced electric field is formed by the grid electrodes (73e, # 0, # 1) (the side surface forms an induced electric field toward the nozzle tip by the voltage-dividing electrode 71e), and a circular nozzle is formed from the nozzle with a narrowed tip. The fusion-produced charged particles (49c) are ejected, neutralized by an electron generator (70e) of a microwave discharge type or the like, and returned to gas.
Charged particles are ejected from a nozzle with a narrowed tip, and a gas that could not be sucked by a high vacuum pump (76h) is rotated to prevent a backflow of the neutralized gas.
In the simple furnace (50s), the charged particles that have passed through the regenerative speed reducer (67E, # 15 to 325) contain a plurality of nuclides and some particles have a low speed. , # 1) are induced by the electric field.
In the cooperative reactor (50c), the charged particles passing through the regenerative moderator (67E, # 11 to 324) are limited to one nuclide and enter at a constant speed after deceleration. It can be converged by the electron lens (73m).

Table 8 is a calculation table of the gas amount when the fusion-produced charged particles (49c) are gasified.
Since tritium (T) and neutrons (n) are not subject to gasification, the gas volumes at one atmosphere are not shown.
When the fusion-produced charged particles (49c) are neutralized and gasified, the ionization neutralizers (70) for the DD reaction and the DD reaction have a density of 1.3 to 2.8 milliliters per second and D- ^3. The He reaction yields 4.1 milliliters of gas per second.
The fusion-produced charged particles (49c) decelerated by the regenerative decelerator (67E) generate approximately 1/32 of a gas in each of the ion neutralizers (70, # 1 to 32). Suction by a high vacuum pump (76h) and pressurized by a plurality of stages of vacuum pumps (76) (not shown in the figure) to obtain gas cylinders (79, # 0, # 1, # 2, Collect in # 4). (In the simple furnace (50s), it is collected in a gas cylinder (79, # 0) without separation.)
Table 8 Calculation table for the amount of recovered gas of fusion product particles

Tritium (T) almost completely disappears in a normal operation state, but when the charged particle beam comes off without colliding, a large amount of tritium (T, about 0.365 μg / bunch) circulates. As shown in the thirteenth ion flow bending device (68r, # 08), it is bent at an angle different from that of the deuterium (D) sent to the ion transfer path (68, # 2), and the ion transfer path (68, # 3). Is separated into
From the ion flow bending device (68r, # 08) of FIG. 12, the ion accelerator (62r, # 11) passes through the ion flow bending device (68r, # 15... # 17) and the regenerative decelerator (67E, # 10). And again extinguishes tritium (T).

When the nuclear fusion reaction using helium 3 ( ³ He) as a fuel is simultaneously performed in one furnace, as shown in Table 7, the tritium (T) and the radius of gyration in the magnetic field are the same, so that separation is difficult as it is. It is.
While arrival time is also possible to separate by providing a kicker (68k) is different, regenerative braking unit (67E, # 10) particle velocity helium ^{3 (3} He) and tritium after regenerative braking by (T) is Since it changes and the radius of gyration in the magnetic field changes, it can be separated by the ion flow bending device (68r, # 17).
Particles having a larger mass-to-charge ratio (m / z) (smaller mass / charge) have a greater deceleration effect.
The ion flow bending device (68, # 17, # 18) is equivalent to the charged particle separator (68x) in that it has the ability to separate a plurality of types of charged particles.

The ion flow bending device (68r, # 17, # 18) separates nuclides of charged particles because the separation amount of foreign nuclei (49s) increases, and the neutralizers (70, # 1, # 2, # 4). ) To provide a transportation route to gas cylinders (79, # 1, # 2, # 4). (Deuterium (D), since helium ⁴ (4 the He) between the mass-to-charge ratio (m / z) are the same, inseparable.
A hydrogen storage alloy (79 m) is incorporated in a gas cylinder (79, # 2, 24) to adsorb deuterium gas (12, D ₂ ) and is separated when taken out. )
When the collision of the charged particle beam comes off, the high-speed particles of the charged particle generator (61, # 0) are temporarily stopped so that the tritium (T) in the fuel particle circulation path (69, # 1) does not increase too much. It is necessary to cooperate to adjust the amount of the reaction and suppress the DD reaction.

<Tritium gas>
As shown in FIG. 13, a charged particle beam fusion reactor (50) of a cooperative type (50c) has a charged particle generator as shown in FIG. 13 in order to secure a disposal method of tritium (T) recovered in a gasified state. (61, # 1) and a particle accelerator (62, # 10). (In the simple furnace of FIG. 10, the separation is not performed.)
The gas collected in the gas cylinder (79, # 0) of the cooperative furnace shown in FIG. 12 is converted into charged particles by the charged particle generator (61, # 1), accelerated by the particle accelerator (62, # 10), and bent by the ion flow. Only tritium (T) is selected by the accelerator (68r, # 18) and sent to the particle accelerator (62, # 11, T) to eliminate tritium (T).

Other particles ^(D, 3 ^{the He,} 4 the He) is ion flow bending device (68r, # 18) ion neutralizer from (70, # 1, # 2, # 4) back to the gas, the gas cylinder (79 , # 1, # 2, # 4).
The ion flow bending device (68r, # 18) is substantially the same as the charged particle separator (68x) in that it separates each nuclide.
In the ion bending device (68r, # 18), occluded gas particles and the like are separated, and are collected in the gas cylinders (79, # 3) via the ion neutralizer (70, # 3).

<Circulation of neutron moderator>
FIG. 14A shows the circulation of the neutron moderator (10) of the tritium annihilation cooperative (50c) charged particle beam collision type fusion reactor (50) of the third embodiment.
The neutron moderator (10) circulating from the bottom to the top in the neutron shielding chamber (67s) and shielding the neutrons (n) is pressurized by the pressurizing pump (87), and the neutron heat conversion at the innermost lowermost part To the vessel (67c).
The plurality of neutron heat converters (67c) circulate from bottom to top, and are heated by irradiation of strong neutrons (n).
The heated neutron moderator (10) is taken out of the upper neutron heat converter (67c), and the turbine (86) is turned to drive the generator (88) to obtain electric power.

The helium 4 gas (24), which is hardly affected by the neutrons (n), is sent to the heat removal chamber (67a), and the neutron moderator (10) is re-heated by the hot helium gas (24). ) Within.
After being cooled by the condenser (89), the neutron moderator (10) returns to the lower part of the neutron shielding chamber (67s) again and circulates.
The neutron heat converter (67c) is irradiated with the neutrons (n) at a place where the neutrons are irradiated with neutrons (n) having sufficient strength and a small neutron reaction cross section (σ _n ) made of a tough material such as ceramic which is hardly activated.
Although water is used as the neutron moderator (10), it absorbs neutrons (n) and changes into deuterium (D), so it is periodically taken out to extract deuterium (D).

<Stop procedure>
The cooperative (50c) stop procedure stops the fast charged particle beam and stops a new DD reaction.
After the tritium (T) particles are sufficiently reduced, the low-speed charged particle generator (61, # 0, D) is stopped.
The kicker (68k, # 1) collects the circulating low-speed charged particle beam deuterium (D) into the gas cylinder (79, # 0) via the ion neutralizer (70, # 0). And shut down the cooperative furnace (50c).
Since the deuterium gas (12) is used, a method of returning to the fuel gas cylinder (12, D ₂ ) is also conceivable. However, since it is a trace amount of gas generated only at the time of stoppage, the gas cylinder is used together with the scattered particles (49s). (79, # 0).

<Example 4: Tritium multiplier>
FIG. 14B shows the circulation of tritium (T) in the tritium multiplication type (50t) charged particle beam collision type fusion reactor (50) of the fourth embodiment.
As the charged particle collision method, one is a deuterium (D), which is easily available, and is a slow charged particle beam having a large number of particles having a diameter of 2 μm, and the other is a deuterium (D) and tritium (T). It has the same configuration as the tritium annihilation cooperative reactor (50c) of the third embodiment in which a high-speed charged particle beam having a small number of particles having a diameter of 1 μm is collided.
In the fourth embodiment, the tritium breeding chamber (67T) filled with the tritium breeding material (LTZO20) processed into a granule and having a tritium breeding rate (η _t ) of 1 or less is heat-exchanged in the cooperating furnace (50c) of the third embodiment. This is a configuration added to the room (67Q).
Beryllium (Be), a neutron multiplier, is added to adjust the tritium growth rate (η _t ).
Irradiated with neutrons (n), tritium breeding chamber (67T) tritium (T), to produce a like helium ^{4 (4} He).

The tritium breeding chamber (67T) connects the upper and lower tritium breeding chambers (67T), and refluxes a helium 4 gas (24) to which 1% deuterium gas (12) is added from a gas cylinder (79, # 4). Tritium (T) generated by neutron (n) irradiation is recovered in the form of hydrogen gas (HT, DT, etc.).
The heat energy (Q) contained in the high-temperature gas collected through the dust collector (83a) is collected by the heat exchanger (84), and the electric power is generated by the turbine (86) and the generator (88). (E) is obtained.
The hydrogen separator (82a) using the hydrogen permeable membrane has the highest activity at 300 ° C to 400 ° C. Therefore, the hydrogen separator (82a) uses the hydrogen separator (82a) using the hydrogen permeable membrane from the heat exchanger (84). A path for returning to the heat exchanger (84) is formed.
The hydrogen is recovered by the hydrogen separator (82a), and the water liquefied by the dehumidifier (83b) (including HTO, etc., is not shown in the figure, but requires treatment), and the compounds are removed. The gas is circulated again by pressurizing with the pressure pump (87).
The hydrogen gas (HT, DT, etc.) containing tritium concentrated by the hydrogen separator (82a) using the hydrogen permeable membrane is collected in a gas cylinder (79, # 0).

The gas (including scattered particles (49s) and the like) collected in the gas cylinder (79, # 0) is sent to the charged particle generator (61, # 1) to be ionized, and ionized by the ion flow bending device (68, # 18). , 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 bending device (68, # 18), the substances are returned to gas by the ion neutralizer (70, # 1, # 2, # 3, # 4), and the gas cylinder ( 79, # 1, # 2, # 3, # 4).
Tritium (T) recovered from the tritium breeding chamber (67T) is added to maintain the DT reaction, and after the tritium (T) has sufficiently increased, reduce the DD reaction to maintain the power generation. Adjust to

<Stop procedure>
After the DD reaction is completely stopped, 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. Then, high-speed tritium (T) is sent to the ion neutralizer (70, # 0), and the furnace is stopped.
After shutting down the furnace, low-velocity fuel particles (D) and tritium gas (13) that could not be extinguished are left in the gas cylinder (79, # 0).

<Example 5 Tritium breeding reactor>
FIG. 15 is a configuration diagram of a tritium breeding (50T) charged particle beam collision type fusion reactor (50) of the fifth embodiment.
As a collision method of charged particles, one is a deuterium (D), which is easily available, a low-speed charged particle beam having a large number of 2 μm particles, and the other is a tritium (T), a high-speed charged particle beam having a small number of 1 μm particles. It is configured to collide with a charged particle beam.
In the fifth embodiment, a tritium breeding chamber (67T) having a tritium breeding rate (η _t ) of 1 or more and a neutron adjustment chamber (67v) are provided.
Since only the DT reaction is required, the fuel particle circulation path (69, # 01) and the charge-mass separator (68x) of the D particles, which are higher in speed than the multiplier (50t) of Example 4, are eliminated. And the number of parts can be reduced.
The recovery path dedicated to tritium (T) for the unreacted fuel particles (49n) is also omitted, and the gas cylinders (79, # 0) are passed through the ion flow bending device (68r, # 04) and the ion neutralizer (70, # 0). 0).
Although not shown in the figure, a heat conversion type can be used by combining a resistor (67R) with the regenerative speed reducer (67E).

The low-speed charged particle beam generator (60, # 0) includes a charged particle generator (61, # 0), a particle accelerator (62, # 00, # 01), and an electron lens (63) for converging the charged particle beam. , And a deflector (64) for adjusting the direction of the beam, and further, an ion recovery path (68c) and a regenerative decelerator (67E, # 00), an ion transfer path (68), and an ion flow bending device. (68r) constitutes the fuel particle circulation path (69, # 0).
A 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 converging the charged particle beam. , A beam deflector (64) for adjusting the beam direction, and a fuel particle circulation path (69, # 1) composed of an ion transfer path (68) and an ion flow bending unit (68r).

The deuterium gas (12) and the triple water gas (13), which are fusion fuels, are ionized by the charged particle generators (61, # 0, # 1), and the charged particles are accelerated by the particle accelerators (62, # 00, # 10). Accelerates to 1 keV to form a pulsed charged particle beam bunch, and sends it out to a fuel particle circulation path (69, # 0, # 1) comprising an ion transfer path (68) and an ion flow bending device (68r). The final acceleration is performed by (62, # 01, # 11).
First, a low-speed beam having a large number of particles and then a high-speed beam are fired with a time lag toward the fusion reaction point (51).

The speed of the charged particle beam to be emitted is a relative speed (slow beam: 1 keV, 300 km / s, high speed beam: 100 keV, 2,520 km / s) at which the fusion reaction cross section (σ) determined by the combination of the fusion fuel is increased. And
In the elongated fusion reaction region (52) headed by the fusion reaction point (51), the launch time and launch direction and the bunch tilt are adjusted so that the entire bunch collides.
The fusion-produced particles (n, 4He) generated by the DT reaction exit out of the 1 μm and 2 μm diameter fuel particle beams in a very short time, and therefore fly isotropically without colliding with other fuel particles. At the speeds shown in Table 5, the particles having the highest speed reach the periphery of the fusion reactor vessel (58) in the order of n, 4He.

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

In a heat exchange chamber (67Q), a tritium breeding chamber (67T) having a tritium breeding rate (η _t ) of 1 or more filled with granular tritium (LTZO20) and neutron multiplier beryllium (Be) and neutron adjustment This is a configuration in which a chamber (67v) is added.
The tritium multiplication rate (η _t ) is adjusted with beryllium (Be), which is a neutron multiplier.
Irradiated with neutrons (n) generated by the nuclear fusion reactions, tritium breeding chamber (67T) tritium (T), to produce a like helium ^{4 (4} He).
The tritium breeding chamber (67T) is connected to the upper and lower tritium breeding chambers (67T) by connecting pipes (67j), and the gas cylinders (79, # 1) and the deuterium gas (12) contained in the gas cylinders (79, # 3). the refluxed 1% added helium 4 gas (24), the recovery occurring particles upon exposure to neutrons (n) (D, T, 4 the ^{He, C)} and concomitant compounds generated by such as gas I do.
Fine particles such as breeding material contained in the recovered high-temperature reflux gas are removed by the dust collector (83a), and the heat energy (Q) is recovered by the heat exchanger (84), and the turbine (86) and the generator (88) ) To generate electric energy (E).

Moisture liquefied by the dehumidifier (83b) (HTO etc. is included, so it is not shown in the figure, but separate treatment is required), compounds, etc. are removed, and hydrogen separation using a hydrogen storage alloy (79m) is performed. Hydrogen and the like (mainly HT molecules and DT molecules) are collected in a gas cylinder (79, # 0) by a vessel (82b), deuterium gas (12) is added, and pressurized by a pressurizing pump (87) to make helium. The four gases (24) are circulated again.
A hydrogen separator (82b) using a hydrogen storage alloy (79m) has two chambers storing a hydrogen storage alloy (79m, # 1, # 2) in a rotating body, and rotates periodically (# 1 （# 2). In one structure (# 1), hydrogen gas (D ₂ , HT, DT molecules, etc.) is occluded, and the other (# 2) is heated to release the occluded gas.

The gas collected in the gas cylinder (79, # 0) is sent to the charged particle generator (61, # 1) to be ionized, and only the tritium (T) is selected by the ion flow bending device (68, # 10). It is sent to the accelerator (62, # 11, T).
Since substances other than tritium (T) are separated by the ion flow bending device (68, # 10), they are returned to gas (mainly H ₂ , HD, D ₂ ) by the ion neutralizer (70, # 1). Collect in gas cylinder (79, # 3). (It is also possible to adopt a configuration in which the deuterium (D) is completely separated.)
A neutron control chamber (67v) is provided, and by adjusting the amount of the neutron moderator (10), the dose of neutrons (n) irradiated to the tritium breeding chamber (67T) is adjusted, and the tritium breeding rate (η) of the entire reactor is adjusted. _t ).
If the excess tritium (T) can be eliminated, for example, by providing a DT reactor having no tritium breeding chamber (67T) adjacent thereto, the neutron conditioning chamber (67v) can be omitted.

<Stop procedure>
After securing the tritium (T) necessary for the start-up, the amount of the neutron moderator (10) in the neutron control chamber (67v) is increased to reduce the tritium multiplication rate (η _t ) and to extinguish the tritium (T). I do.
The charged particle generator (61, # 1) is stopped, and the high-speed charged particle beam is stopped.
Next, the charged particle generator (61, # 0) is stopped.
The circulating low-speed charged particle beam is changed in deflection intensity of the ion flow bending device (68r, # 04) and sent to the ion neutralizer (70, # 0) to give electrons to neutralize the gas. (79, # 0) and shut down the furnace.

Deuterium in abundance on the earth (D, deuterium) or lithium (Li) of the fusion reaction is generated as the first fuel, helium 3 with obtaining electrical energy, a secure fusion fuel (3 ^{the He)} Or a neutron (n) or tritium (T) is immediately annihilated to provide a fusion power generation and a fusion engine with less influence of radioactivity.

# 00 Individual identification number for each drawing η _f Fusion reaction rate η _Q Thermal efficiency η _t Tritium production rate μ / μ ₀ Specific permeability ρ Density λe Mean 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 Ultra 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 (truncate icosahedron, etc.)
³ He helium 3 (helium 3 nucleus) ⁴ He helium 4 (helium 4 nucleus)
49 charged particles 49c fusion product charged particles 49f final fusion product particles ^(p, 4 He)
49n Unreacted fuel particles 49s Scattered particles, charged particles, and foreign nuclei 50 Charged particle beam collision-type fusion reactor 50c Tritium annihilation coordination type (coupling reactor)
50t tritium multiplication type (multiplier furnace) 50T tritium breeder type (breeder furnace)
50s Simple type (simple furnace) 50h Heat conversion type (heat conversion furnace)
51 Nuclear fusion reaction point 52 Fusion reaction area 53 Center of reactor
55 Vacuum container 56 Charged particle concentrator 56g Charged particle rectifier
58 fusion reactor vessel 59 outer wall 60 charged particle beam generator
61 charged particle generator
62 particle accelerator
63 electron lens 63c capillary 63e electrostatic electron lens 63m magnetic field electron lens 64 deflector
64e Electric field type deflector 64m Magnetic field type deflector 67 Energy converter 67E Regenerative decelerator 67l Ion circuit 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 shield room 67T Tritium breeding room 67v Neutron adjustment room

68 Ion transfer path 68c Ion recovery path 68k Kicker 68x Charged particle separator 68r Ion flow bending device 68b Particle recovery device 68m Fan magnetic field 68s Scattered particle separator 69 Fuel particle circulation path 70 Ion neutralizer 70e Electron generator 71 Electrode 71e Voltage dividing electrode 72 Magnetic body 73e Aspheric grid electrode 73m Magnetic field type electron lens 76 Vacuum pump 76h High vacuum pump 79 Gas cylinder 79m Hydrogen storage alloy 80 Fusion propulsion machine 80j Fusion jet engine 81 Fusion thermoelectric 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 Pressurized pump 88 Generator 89 Condenser

Charged particle beam collision-type fusion is a method that is known to reliably generate fusion, but since it has been used only for research so far, it can be configured for power. To consider.
In the DD reaction, the collision requires 500 keV and kinetic energies (K) of 3.27 MeV and 4.03 MeV are obtained. Therefore, the kinetic energy (K) is 7.3 times the average of the input kinetic energy (K). can be obtained, if the efficiency of particle acceleration instrument (eta _a) is 5% or less, it is not possible to achieve a break-even.
The acceleration efficiency (η _a ) of the recently developed distributed accelerators (Patent Literature 3, Patent Literature 4, Non-Patent Literature 3) is 60%, so that a break even can be achieved.
As a result of the study, we will select “Fusion charged particle beam collision type fusion that can separate fusion fuel particles and fusion generated charged particles” as the fusion reactor method.

Inside the particle accelerator (62), when a part of the charged particle beam comes into contact with an electrode or a metal part of the accelerator, an accident may occur that the metal is melted.
An insulating container made of strong engineering ceramics is provided between the charged particle passage and the electrode to prevent accidents.
The scattered charged particles come into contact with the inside of the insulating container to cause charging, which affects the trajectory of the charged particle beam. Therefore, it is necessary to remove the charging.
For this reason, after imparting appropriate conductivity, or after emitting charged particles, an acceleration operation is performed in the absence of charged particles, and charge is removed by a strong electric field.

<Capillary>
The capillary (63c) converges charged particles by using a tapered tube structure made of a tough insulator such as engineering ceramics and having one thinned portion.
The charged particles incident on the inner wall surface of the capillary (63c) at a small angle are totally reflected and the charged particles are squeezed according to the gradually narrowing inner diameter of the tube. (63m) converges on a different principle.
Two or more capillaries (63c) can be arranged side by side in the same direction.

Even after leaving the tip of the capillary (63c), the charged particles try to go straight due to the inertia of each particle, so that the charged particle beam can be narrowly converged at a certain distance.
An electrode is provided outside the capillary (63c), a pulse voltage is applied to prevent charged particles from remaining inside the capillary (63c), and a pulse voltage is applied with no load to perform the removal operation.
The convergence of the charged particles by the capillary (63c) is considered to be a guiding effect by charged particles on the inner surface of the insulator capillary (63c) such as a single crystal or polycrystalline engineering ceramics, but is due to the nuclei constituting the metal capillary. It has been confirmed that charged particles can be converged by small-angle forward scattering. (Patent Document 5)

^{Although the 3} He- ³ He reaction was not listed in the calculation table of Table 4, the fusion reaction cross-sectional area (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 higher by one to two orders of magnitude.

When the density of the charged particle beam is high, the nuclear fusion reaction rate (η _f ) is significantly increased. Therefore, it is assumed that the beam density is converged to 0.1 μm to 0.3 μm to increase the beam density by 10 to 100 times. .
Since the neutron (n) generation rate can be considered to be the product of the heteroatom mixing rate contained in the fuel particles, if the D particle mixing rate is 10 ⁻⁹ , the neutron (n) generation rate is 10%. ^It has an excellent feature that it is extremely small at ^-18 .
If available combinations of fusion fuel of D-3 ^He reaction is not separately shown, ³ He-3 combination of fusion fuel of ^He reaction is also available.

The shape of the charged particle concentrator (56) near the focal point far from the fusion reaction point (51) is gradually narrowed, and the charged particles are gradually focused.
Since the base ellipse has been modified, the path of particles incident and reflected at the periphery is about 8.5% longer in the case of a truncated icosahedron than the path of particles incident at the center. Become.
Therefore, by setting the axis at an angle to the arrival direction of the particles, it is possible to arrange the low-speed particles so as to pass through a short path and the high-speed particles through a long path. Can be corrected.
The charged particle concentrator (56) is made of a tough insulator material such as engineering ceramics, and on the outside thereof, electrodes (71, # 1 to 3) for removing charge are provided to apply a positive high voltage. In addition, the fusion-produced charged particles (49c) are prevented from being charged.
A high voltage is applied in a pulsed manner from the center side to the outer electrodes (71, # 1 to # 3) in order to remove charged charged particles.
When a current flows through the electrode (71) with the passage of the fusion-produced charged particles (49c), the kinetic energy (K) of the charged particles is reduced. Shape.

Table 5 (a) Calculation table of mass-to-charge ratio (m / z) and radius of gyration

Table 5 (a) shows a calculation table of the mass-to-charge ratio (m / z) and the radius of gyration in a magnetic field of 1 Tesla.
Since the rotation radius of the magnetic field of tritium (T) and helium 3 (3 ^He) is different, it can be easily separated.
The tritium (T) and the proton (p) of the fusion-produced charged particles have the same radius of gyration in the magnetic field, so it is difficult to separate them by the magnetic field alone. Separating by the speed difference until reaching.
In the case of performing D-D reaction and D-T reactions simultaneously, helium 4 (4 ^He) is applied, come to fly to the second, but since it is almost the same as the rotation radius of tritium (T), separated Is difficult.
Helium ⁴ as (4 the He) can be separated at a flying speed difference, D-T reaction is generated immediately before the D-D reactions, first flight to come protons (p) and the second helium ⁴ (4 the He ), A negative deflection voltage is applied to the outer electrode (71, # 1), a positive deflection voltage is applied to the inner electrode (71, # 2), and the proton (p) and helium are directed outward. 4 ( ⁴ He) is accelerated and separated.
Table. 5 (b), based on the radius fusion reaction point (51) helium 4 (4 ^{the He)} after 0.5μ seconds to reach, in which set a arrival time of each fusion product particles by direction .
The position of helium 4 ( ⁴ He) after 0.5 μs becomes a spherical shell centering about 1.7 m below the fusion reaction point (51), so that the charged particle separator (68x ), The center of the deflection magnetic field is arranged, the magnetic field intensity changes from weak to strong at 0.4 μS as a boundary, so that four types of particles can be separated in the charge mass separator (68x) in any direction. It is.
The arrival time difference between the proton (p) and the tritium (T) is about 0.07 μS faster in the upward direction when comparing the upward direction (10 °) and the downward direction (170 °). Therefore, the flight distance to the charge-mass separator (68x) can be shortened, and the size of the furnace can be optimized (miniaturized).
Table 5 (b) helium ^{4 (4} He) particles per flying direction relative to the ^{(p, 4 He, 3 H} , 3 He) of the arrival time

Incidentally, tritium (T) and helium 3 (3 ^He) may be but not be sufficiently separation by arrival time difference, and the specific orbital radius is significantly different, separated by the deflection magnetic field of the charge mass separator (68X) it can.
When the DD reaction is performed alone, the intensity of the deflection magnetic field may be changed from weak to strong based on 0.5 μS, and the margin is large.
When the DD reaction and the DT reaction are performed simultaneously, the DT reaction is advanced by 0.03 μS to 0.3 μS before the DD reaction to avoid collision between high-speed fuel particles and to reduce helium 4 the arrival time (4 ^{the He)} early, it is possible to ensure the separation of tritium (T) of the fusion product particles.
If the particle separation accuracy can be improved, the standard of 0.5 μS can be shortened, and the furnace can be further reduced in size.
Protons (p) and helium 4 ( ⁴ He) can be separated by a deflecting magnetic field, but are located on the outermost side because the deflecting magnetic field is weak. Since both are discarded substances, there is no particular problem if they cannot be separated.
A different separation method is also possible by using a deflecting magnetic field that continuously lowers the intensity of the deflecting magnetic field by about half during the time from 0.2 μs to 1.5 μs after the onset of fusion. The resulting particles can be separated.
Separation order, an outer ^T, 4 the He, in the order of ^p, 3 the He.
Particles having different velocities are included for each nuclide, but particles that arrive at an earlier speed and pass through a slightly stronger deflecting magnetic field and are slightly more strongly deflected can be used to improve the separation accuracy of charged particles.

The regenerative speed reducer (67E, # 10) has a limited length that can be installed, and if the charged particles are excessively decelerated, the charged particles separated by the arrival time difference may be mixed. After that, separation by a charged particle separator (68x) is performed.
The intensity of the deflecting magnetic field and electric field required for the charged particle separator (68x) can be slightly reduced by decelerating the fusion-produced charged particles (49c) separated by the arrival time difference in a range where they do not mix again.
Particles having a smaller mass-to-charge ratio (m / z) have a greater deceleration effect, and therefore have a different radius of gyration in a magnetic field.
Therefore, it is also effective to decelerate by passing through the regenerative speed reducer (67E), change the specific orbital radius in the magnetic field, and then separate by the charged particle separator (68x).
Fusion switching particles (49c) can be separated without switching the intensity of the deflection magnetic field.

Since the charged particle separator (68x) and the regenerative moderator (67E) can be a path through which the neutrons (n) leak to the outside, the central axis of the regenerative moderator (67E) is moved relative to the fusion reaction point (51). By detaching and attaching, and by arranging the bent portion of 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 performing combined ^D-3 the He reaction, fast proton 14MeV to fusion product charged particles (49c) (p) is applied.
Since the speed of the scattered particles (49s) generated at the time of the collision of the charged particles or the charged particle beam having the static elimination is lower than that of the fusion-produced charged particles (49c), the innermost regenerative decelerator (67E, # 15) is used. Be guided.

<Regenerative reducer>
It is made of tough cylindrical engineering ceramics that can withstand the irradiation of charged particles. Electrodes that are electromagnetically coupled to the charged particles are formed on the outside, and the kinetic energy (K) of the charged particles is directly converted to electric energy (E).

Table 6 Neutron dose calculation table

Table 6 is a neutron dose calculation table of the cooperative reactor (50c) and the simple reactor (50s).
In both cases, the annual exposure limit (1 mSv / year) of ordinary people is reached in 1 to 4 days.
In the associated reactor (50c) for performing the DD and DT reactions of 200 MW shown in FIG. 4, 14.6 × 10 ¹⁹ neutrons (n) of 2.45 MeV and 14 MeV are generated, and a 20 m radius of 20 m is generated. At the point, the effective dose of neutrons (n) permeating through a 5 m thick layer of water is 0.277 mSv / day, taking into account the coefficients. (In this calculation table, neutrons (n) are all 14 MeV. If the water thickness is 6 m, the annual exposure of ordinary people can be reduced, but the charged particle separator (68x) and the regenerative decelerator (67E) 5 m because the thickness of the water in the storage portion such as decreases.)
The heat exchange chamber (67Q) has many penetrating portions, and neutrons (n) penetrating therethrough exist.
Since the neutron (n) level is high in the vicinity of the deflection coil of the charge-mass separator (68x), a semiconductor switch cannot be arranged. Therefore, using a wiring with a small parasitic inductance or the like, a semiconductor is placed in a position with a low neutron (n) level. Place the switch.
Since the water having a thickness of 5 m can be expected to have an attenuation of about 3.2 × 10 ⁻¹⁴ , the surface dose is reduced to about 1.1 Bq / cm ² at a position apart from the opening such as the charged particle converging device (56). Therefore, it is possible to install a semiconductor.
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 that the annual exposure is below the allowable amount for ordinary people.
A light-weight neutron reflector (67b) is incorporated to reduce the neutron moderator (10), and a strong structural material such as low activation ferritic steel is required. These are included as neutron shields and reflectors. be able to.
Further, a part of the outer neutron shielding chamber (67s) having a small calorific value can be replaced with a light-weight solid neutron shielding body (67p) or the like.

When neutron (n) reacts with helium 3 ( ³ He) as a fusion fuel, it changes to tritium (T).
³ He + n → T + p + 0.764MeV
Since the amount of neutron emission from the simple reactor (50s) depends on the content of impurities in the fusion fuel, it is necessary to use a fusion fuel that has been sufficiently purified and store it while avoiding irradiation with neutrons (n). Immediately before colliding with helium 3 ( ³ He) as a fusion fuel, when it is bent by an ion flow bending device (68r) or the like, the different nuclei (49s, D particles, T It is important that particles (such as particles) are sufficiently removed.
The effect of separating and removing foreign nuclei (49 s, D particles, T particles, etc.) is great. If the mixing ratio of foreign atoms is made 1/1000, the neutron moderator (10) has a neutron shielding room (50 cm thick). 67s) can be reduced.
In the case of a moving body, the load factor and operating time of the furnace can be taken into account.
There is also a method of providing a shielding plate made of a material having a large neutron shielding effect between an occupant and a fuel tank.

FIG. 9 (b) is the lithium to be used in magnetic confinement type blanket fusion reactor (Li), beryllium (Be) tritium breeding chamber filled with material comprising (67T) of the heat exchange chamber plus (67Q) .
The tritium breeding chamber (67T) is filled with a lithium compound (LTZO20) as a tritium breeding material and beryllium (Be) as a neutron multiplier, and the upper and lower tritium breeding chambers (67T) are connected by a connection pipe (67j). ing.
The helium 4 gas (24) to which a gas such as hydrogen (11, 12) of about 1% is added is refluxed to collect particles (D, T, 4He, C) generated by irradiation with neutrons (n). .
The thermal energy (Q) contained in the recovered high-temperature gas is recovered, power is generated by heat, and electric energy (E) is obtained.
The recovered circulating gas contains about 1% of a gas such as hydrogen (11, 12) and about 0.01% of a tritium gas (13) with respect to the helium 4 gas (24), and contains carbon (C) and these gases. Fine powder such as the compound and breeding material.
The gas such as hydrogen (11, 12, 13) is concentrated using a hydrogen separator (82a) using a palladium alloy membrane (an alloy in which Ag, Pt, Au, etc. are mixed in a small amount in 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 and other gases (11, 12, 13) and heats. There is also a method of concentrating a gas such as hydrogen by using a hydrogen separator (82b) that releases hydrogen.
The concentrated gas such as hydrogen is sent to the charged particle generator (61), ionized, and only tritium (T) is selected based on the mass-to-charge ratio (m / z). Allow fusion reaction.
It is also conceivable to liquefy the recovered gas and separate it using the difference in boiling point.

Behavior of fusion particles in DD reaction Behavior of fusion particles in DT reaction Behavior of fusion particles in D-3He reaction Tritium annihilation-linked charged particle beam collision type fusion reactor (DD, DT reactor) Simplified charged particle beam collision type fusion reactor (D-3He reactor) Flight of fusion-produced particles (a) to (e) DD reaction, (f) DD and DT reaction (A) charged particle concentrator, (b) charged particle separator, (c) polyhedron Regenerative reducer (a) Electrostatic coupling type, (b) Magnetic coupling type, (c) Resistor load type (A) Neutron heat conversion room, (b) Tritium breeding room Simplified charged particle beam collision type fusion reactor (Example 1) Thermal conversion type charged particle beam collision type fusion reactor (Example 2) (a) Longitudinal sectional view, (b) Transverse sectional view, (c) Nuclear fusion power generation device composed of a thermal conversion furnace Tritium annihilation cooperative reactor ( Example 3) (a) Main configuration (b) Heat circulation configuration (A) ion flow bending device, (b) ion neutralizer Tritium multiplier (Example 4) (a) Main configuration, (b) Configuration of heat circulation and tritium recovery Configuration of tritium breeder reactor (Example 5)

<Example 1: Simple furnace>
FIG. 10 is a configuration diagram of the simplified (50 s) charged particle beam collision type fusion reactor (50) of the first embodiment.
As a charged particle collision method, one is a low-speed charged particle beam having a large number of 2 μm diameter particles of deuterium (D), which is easily available, and the other is a small number of 1 μm diameter particles of helium 3 ( ³ He). The system is configured to collide a high-speed charged particle beam to cause a fusion reaction of the charged particles without waste.
The low-speed charged particle beam generator (60, # 0) includes a charged particle generator (61, # 0), a particle accelerator (62, # 00, # 01 ), and an electron lens (63) for converging the charged particle beam. ) And a deflector (64) for adjusting the direction of the beam, and further, an ion recovery path (68c), a regenerative decelerator (67E, # 00), an ion transfer path (68), and an ion flow bending device. A fuel particle circulation path (69, # 0) composed of (68r , # 01 to # 05 ) is used to reuse the fuel particles.
A charged particle beam generator (60, # 1 ) for high speed includes a charged particle generator (61, # 1), a particle accelerator (62, # 11) , an electron lens (63) for converging a charged particle beam, and a beam. And a deflector (64) for adjusting the direction of .
Further, the high-speed and low-speed unreacted fuel particles of the charged particles are recovered by using one recovery path by the ion recovery path (68c) and the regenerative speed reducer (67E, # 00).

<Example 2: Heat conversion furnace>
FIG. 11 is an explanatory view of a heat conversion type (50h) charged particle beam collision fusion reactor (50) of the second embodiment.
As a collision type of charged particle, a simple furnace (50s) and similar, one of the charged particle beam slow often the number of particles diameter 2μm of readily available deuterium (D), the other is helium 3 (3 ^He) A high-speed charged particle beam having a small number of particles having a diameter of 1 μm is caused to collide, and the charged particles undergo a fusion reaction without waste.
FIG. 11 (a) is a longitudinal sectional view, and the whole shape is a truncated cone. FIG. 11 (b) is a transverse sectional view, and a charged particle concentrator forming a reflection surface based on a radially elliptical surface rotating to the right. (56, # 1 to 10) and an ion orbiting speed reducer (67l) formed of a single thread groove provided therearound.
The fusion-produced charged particles (49c) generated in the fusion reaction region (52) are reflected on one surface of the charged particle converger (56, # 1 to 10), and each charged particle bunch is provided around. It is led to the ion orbital decelerator (67l) and rotates rightward in FIG. 11 (b).
A charged particle rectifier (56 g, shown by a dashed line) is disposed inside the charged particle concentrator (56), and the charged particles flying in a direction close to the axis are guided to the ion circulation speed reducer (67l). (The charged particle rectifying plate (56g) does not exist in the heat exchange chamber (67Q).)

<Example 3: Cooperating furnace>
Figure 12 (a) is a block diagram of a tritium disappearance Federated Example 3 (50c, D-D, D-T reactor) charged particle beam collision type fusion reactor (50).
As the collision method of charged particles, one is a deuterium (D), which is easily available, and is a low-speed charged particle beam having a large number of particles having a diameter of 2 μm, and the other is a deuterium (D) and tritium (T). A high-speed charged particle beam having a small number of particles having a diameter of 1 μm is caused to collide with each other so that the charged particles undergo a nuclear fusion reaction without waste.
The low-speed charged particle beam generator (60, # 00) includes a charged particle generator (61, # 0), a particle accelerator (62, # 0, # 00), and an electron lens (63) for converging the charged particle beam. And a deflector (64) for adjusting the direction of the beam,
Furthermore, an ion recovery path (68c) and a regenerative speed reducer (67E, # 0), an ion transfer path (68), and a fuel particle circulation path (69, # 00) composed of an ion flow bending device (68r) are configured. Then, deuterium (D), which is a low-speed unreacted fuel particle (49n), is reused.

A 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 converging a charged particle beam. , A deflector (64) for adjusting the beam direction, and a fuel particle circulation path (69, # 01) composed of an ion transfer path (68) and an ion flow bending unit (68r). Deuterium (D), which is an unreacted particle (49n), is reused.
The associated reactor (50c) uses deuterium (D), which is readily available, as the first fusion fuel for the low and high speed beams.
Another high-speed charged particle beam generator (60, # 1) includes a particle accelerator (62, # 11), an electron lens (63) for converging a charged particle beam, and a deflector (60) for adjusting the beam direction. 64), the tritium (T) generated by the DD reaction is separated and decelerated by a charged particle separator (68x) and a regenerative speed reducer (67E, # 14 to 324), and circulated as charged particles. ing.
Although not shown, a regenerative reducer (67E) can be added to the resistor (67R) to make it a heat conversion type, and a regenerative reducer (67E) behind the charged particle separator (68x) is It can be replaced with an ion orbital decelerator (67l) that is connected in an annular shape, and can be configured to be commonly used for each nuclide among a plurality of charged particle separators (68x).

The deuterium gas (12) is sent to the charged particle generator (61, # 0) to be ionized, sent to the particle accelerator (62, # 0), and includes an ion transfer path (68) and an ion flow bending device (68r). The fuel is sent to the fuel particle circulation path (69, # 00, # 01).
The length of the particle accelerator (62) is of more than several tens of meters is common, the ion transfer path of FIG. 12 (a) (68) and particle accelerator (62) is drawn shorten the length I have.
The length of the ion transfer path (68) is determined in consideration of the nuclear fusion generation cycle (1 / f), the transit time of the particle accelerator (62), and the like.

Tritium (T) passes through the fusion fuel particle circulation path (69, # 1) composed of a dedicated ion transfer path (68) and an ion flow bending device (68r, # 11 to 13), and the charged particles are discharged. As it is, it is transported to the particle accelerator (62, # 11, T), accelerated to 100 keV, and fired so as to collide with the low-speed D particles just before the high-speed D particles collide.
FIG. 12 (a) shows only one fusion fuel particle circulation path (69, # 1) dedicated to tritium (T), but the number of charged particle concentrators (the same as the number of faces of the polyhedron (32)) is shown. 56, # 1 to 32), a large number of ion flow bending devices (68r) and an ion transfer path (68) are combined to form a single charged particle flow, and the particle accelerator (62, # 11, T ) To transport.

The unreacted fuel particles (49n) that have passed through the fusion reaction region (52) without performing fusion, as shown in Table 4, have a low fusion reaction rate (η _f ) of D particles, so The particles are circulated and reused.
The unreacted fuel particles (49n) are recovered from the ion recovery path (68c) provided at the lower part of the fusion reactor vessel (58) and reused.
The unreacted fuel particles (49n, D) of the low-speed beam are supplied to the fuel particle circulation path (69, # 00, # 01) for the deuterium (D) constituted by the ion flow bending device (68r) and the ion transfer path (68). ) via a charged particle generator (61, # 0) and the particle accelerator (62, # 0) or La Defense Yuteriumu (D) adding, particle accelerators (62 for low speed, is sent to # 00), Reuse.
The unreacted fuel particles (49n, D) of the high-speed beam are decelerated by the regenerative speed reducer (67E, # 0), circulated to the high-speed particle accelerator (62, # 01) and reused.

Although not shown in the figure, the amount, the arrival position, and the time of the charged particle beam are detected from the voltages, the voltage deviations, and the times generated in the plurality of annularly arranged electrodes in the ion collection path (68c). Equipped with a sensor, it acquires data necessary for grasping the collision state.
The charged particle concentrator (56) is given a role as a vacuum vessel (5 5 ), and circulates helium 4 gas (24) to the surrounding heat removal chamber (67a) to cool the equipment and recover heat. Do.

<Ion flow bending device>
FIG. 13A shows an ion flow bending device (68 r, # 03, # 08) and an ion neutralizer (70) corresponding to FIG. 12 and configured by two fan-shaped magnetic fields (68 m, # 03, # 08). FIG.
The ion flow bending device (68r) can bend the flow of the charged nuclide particles in any direction using a sector magnetic field (68m), a sector electric field (68e), or both. In this application, a fan-shaped magnetic field (68 m) will be described.
Table 7 is a calculation table of the radius of gyration in a magnetic field of 1 Tesla with respect to the velocity of the fuel particles.
The ion flow bending device (68r) bends the flow of charged nuclide particles by a fan-shaped magnetic field.
The basic bending angles of the ion flow bending device (68r) shown in FIGS. 10 to 15 are all illustrated as 90 °, but this is due to the convenience of the plan view for explanation, and actually Designs the basic bending angle depending on the three-dimensional arrangement.
The nuclide particles and the particles having different velocities, which are not transported, are ejected at an angle different from the basic bending angle, so that the charged particle stream can be purified together.
Table 7 Calculation table of radius of gyration of fuel particles in magnetic field

The ion flow bending device (68r) and the ion neutralizer (70) are made of an insulating material such as engineering ceramics, and prevent an accident due to contact of charged particles with the electrode.
Although not shown in the drawing, an electrode (71) is provided on the outer surface of the insulating material, also on the pole face.
In a time zone where charged particles do not enter, a pulsed high voltage is applied to these electrodes (71) to remove charged charged particles.

Tritium (T) is in a normal operation state disappears almost completely, if the charged particle beam is out without colliding, a large amount of tritium (T, about 0.365μg / banch) from circulates, Deyute It is bent at an angle different from that of the lithium (D), and is not the ion transfer path (68, # 2) of the ion flow bending device (68r, # 08) shown in FIG. ).
As shown in FIG. 12A, tritium (T) is supplied from the ion flow bending device (68r, # 08) to the ion flow bending device (68r, # 15... # 17) and the regenerative speed reducer (67E, # 10). through, feeding the particle accelerator (62, # 11), again, perform the disappearance.

<Tritium gas>
As shown in FIG. 12 (a) , the associative (50c) charged particle beam collision-type fusion reactor (50) secures a disposal method for tritium (T) and the like recovered in a gasified state. It is configured to include a charged particle generator (61, # 1) and a particle accelerator (62, # 10). (The simple furnace of FIG. 10 is not provided because it does not separate the fusion-producing particles .)
The gas collected in the gas cylinder (79, # 0 ) of the cooperative furnace shown in FIG. 12 (a) is converted into charged particles by the charged particle generator (61, # 1), and accelerated by the particle accelerator (62, # 10). Only tritium (T) is selected by the ion flow bending device (68r, # 18) and sent to the particle accelerator (62, # 11, T) to extinguish the tritium (T).

Other particles ^(D, 3 ^{the He,} 4 the He) is ion flow bending device (68r, # 18) ion neutralizer from (70, # 1, # 2, # 4) back to the gas, the gas cylinder (79 , # 1, # 2, # 4).
The ion flow bending device (68r, # 18) is substantially the same as the charged particle separator (68x) in that it separates each nuclide.
In the ion flow bending device (68r, # 18), occluded gas particles and the like are separated, and are collected in the gas cylinders (79, # 3) via the ion neutralizer (70, # 3).

<Circulation of neutron moderator>
Figure 1 2 (b) shows the circulation of the neutron moderating material (10) of the charged particle beam collision type fusion reactor tritium disappearance Federated Example 3 (50c) (50).
The neutron moderator (10) circulating from the bottom to the top in the neutron shielding chamber (67s) and shielding the neutrons (n) is pressurized by the pressurizing pump (87), and the neutron heat conversion at the innermost lowermost part To the vessel (67c).
The plurality of neutron heat converters (67c) circulate from bottom to top, and are heated by irradiation of strong neutrons (n).
The heated neutron moderator (10) is taken out of the upper neutron heat converter (67c), and the turbine (86) is turned to drive the generator (88) to obtain electric power.

The helium 4 gas (24), which is hardly affected by the neutrons (n), is sent to the heat removal chamber (67a), and the neutron moderator (10) is re-heated by the hot helium gas (24). ) Within.
After being cooled by the condenser (89), the neutron moderator (10) returns to the lower part of the neutron shielding chamber (67s) again and circulates.
The neutron heat converter (67c) is irradiated with the neutrons (n) at a location where the neutrons are irradiated with neutrons (n), which is made of a tough material such as engineering ceramics having a sufficient strength and a small neutron reaction cross section (σn) which is hardly activated.
Although water is used as the neutron moderator (10), it absorbs neutrons (n) and changes into deuterium (D), so it is periodically taken out to extract deuterium (D).

<Example 4: Tritium multiplier>
Figure 14 (a) is a configuration diagram of a charged particle beam collision突型fusion reactor tritium multiplying Example 4 (50t) (50).
As the charged particle collision method, one is a deuterium (D), which is easily available, and is a slow charged particle beam having a large number of particles having a diameter of 2 μm, and the other is a deuterium (D) and tritium (T). It has the same configuration as the tritium annihilation cooperative reactor (50c) of the third embodiment in which a high-speed charged particle beam having a small number of particles having a diameter of 1 μm is collided.
In addition to changing the neutron heat exchanger (67c) to a tritium breeding chamber (67T) and providing a recovery path for breeding tritium (T), a tritium annihilation cooperative reactor (50c) and a tritium multiplier (50t) Since the configuration is the same, duplicate description will be omitted.
The tritium breeding chamber (67T) is a tritium breeding chamber (67T) filled with granular tritium breeding material (LTZO20) and having a tritium breeding rate (ηt ) of 1 or less.
Beryllium (Be), a neutron multiplier, is added to adjust the tritium growth rate (ηt).
Irradiated with neutrons (n), tritium breeding chamber (67T) tritium (T), to produce a like helium ^{4 (4} He).

FIG. 14B shows a circulation path for collecting tritium (T) generated in the tritium breeding chamber (67T).
The tritium breeding chamber (67T) connects the upper and lower tritium breeding chambers (67T), and refluxes a helium 4 gas (24) to which 1% deuterium gas (12) is added from a gas cylinder (79, # 4). Tritium (T) generated by neutron (n) irradiation is recovered in the form of hydrogen gas (HT, DT, etc.).
The heat energy (Q) contained in the high-temperature gas collected through the dust collector (83a) is collected by the heat exchanger (84), and the electric power is generated by the turbine (86) and the generator (88). (E) is obtained.
The hydrogen separator (82a) using the hydrogen permeable membrane has the highest activity at 300 ° C to 400 ° C. Therefore, the hydrogen separator (82a) uses the hydrogen separator (82a) using the hydrogen permeable membrane from the heat exchanger (84). A path for returning to the heat exchanger (84) is formed.
The hydrogen is recovered by the hydrogen separator (82a), and the water liquefied by the dehumidifier (83b) (including HTO, etc., is not shown in the figure, but requires treatment), and the compounds are removed. The gas is circulated again by pressurizing with the pressure pump (87).
The hydrogen gas (HT, DT, etc.) containing tritium concentrated by the hydrogen separator (82a) using the hydrogen permeable membrane is collected in a gas cylinder (79, # 0).

<Example 5 Tritium breeding reactor>
FIG. 15 is a configuration diagram of a tritium breeding (50T) charged particle beam collision type fusion reactor (50) of the fifth embodiment.
As a collision method of charged particles, one is a deuterium (D), which is easily available, a low-speed charged particle beam having a large number of 2 μm particles, and the other is a tritium (T), a high-speed charged particle beam having a small number of 1 μm particles. It is configured to collide with a charged particle beam.
In the fifth embodiment, a tritium breeding chamber (67T) having a tritium breeding rate (ηt) of 1 or more and a neutron conditioning chamber (67v) are provided.
In the case of the configuration using only the DT reaction, the fuel particle circulation path (69, # 01) of the D particles, the charged particle separator (68x), and the like are faster than the multiplier (50t) of the fourth embodiment. taken was divided, there is a feature that can be simplified structure.
Although not shown in the figure, it is also possible to select a charged particle concentrator (56) and an ion orbital decelerator (67l) having a star-shaped cross section as shown in Example 2. .
The recovery path dedicated to tritium (T) for the unreacted fuel particles (49n) is also omitted, and the gas cylinders (79, # 0) are passed through the ion flow bending device (68r, # 04) and the ion neutralizer (70, # 0). 0).
_

The gas collected in the gas cylinder (79, # 0) is sent to the charged particle generator (61, # 1) to be ionized, and only the tritium (T) is selected by the ion flow bending device (68r, # 10). It is sent to the accelerator (62, # 11, T).
Since substances other than tritium (T) are separated by the ion flow bending device (68r, # 10), the ions are returned to the gas (mainly H2, HD, D2) by the ion neutralizer (70, # 1), and the gas cylinder ( 79, # 3). (It is also possible to adopt a configuration in which the deuterium (D) is completely separated.)
By providing a neutron control chamber (67v) and adjusting the amount of the neutron moderator (10), the dose of neutrons (n) irradiated to the tritium breeding chamber (67T) is adjusted, and the tritium breeding rate (ηt) ) Control.
If the excess tritium (T) can be eliminated, for example, by providing a DT reactor having no tritium breeding chamber (67T) adjacent thereto, the neutron conditioning chamber (67v) can be omitted.
Furthermore, although not shown in the figure, the tritium breeding chamber (67T) is unevenly distributed in the lower part of the furnace, and the firing time of the charged particle beam is adjusted to change the position of the fusion generation point (51), thereby allowing the tritium breeding to be performed. The rate (ηt) can be controlled.

Claims (8)

Of the two fusion fuel beams that are launched, one is a slow charged particle beam and the other is a fast charged particle beam.
Both are deuterium (D); and
Deuterium (D) and tritium (T)
What is deuterium (D) and helium ^{3 (3} He), and,
Are those helium ^{3 (3} He) to both,
It is configured to increase the number of low-speed charged particles compared to high-speed charged particles,
A particle accelerator (62) for accelerating charged particles as a fusion fuel by Coulomb force to bunch a pulsed charged particle beam, an electron lens (63) for converging the charged particle beam, and a flight direction of the charged particle beam A high-speed and low-speed charged particle beam generator (60), comprising a deflector (64) for changing
An energy converter (67) arranged to surround the fusion reaction region (52) with which the charged particle beam collides, for obtaining the kinetic energy (K) of the fusion-producing particles;
A fuel particle circulation path (69) including an ion collection path (68c) for collecting the charged particle beam, an ion transfer path (68), and an ion flow bending device (68r);
The charged particle beam generator (60) sequentially emits a low-speed and then a high-speed charged particle beam and converges on the fusion reaction point (51);
Collision occurs at a relative velocity at which the fusion reaction cross section (σ) determined by the combination of fusion fuels increases (the velocity at which the kinetic energy (K) obtained by nuclear fusion increases with respect to the kinetic energy (K) required for collision). To generate a fusion reaction in the elongated area,
The energy converter (67) obtains the kinetic energy (K) of the fusion product particles flying isotropically in a pulse form from the fusion reaction region (52), and decelerates the kinetic energy.
Unreacted fuel particles (49n) that have passed through the fusion reaction region (52) without performing a nuclear fusion reaction from the ion recovery channel (68c) are recovered, and charged via the fuel particle circulation channel (69). Circulate through the particle accelerator (62) without stagnation in the state of particles and reuse it;
A charged particle beam collision-type fusion reactor (50) comprising the fuel particle circulation path (69).
Fusion fuel of charged particle beam, one of which is slow and the other is fast,
What is deuterium (D) and helium ^{3 (3} He), and,
Are those helium ^{3 (3} He) to both,
An energy converter (67) that obtains the kinetic energy (K) of the fusion-producing particles,
A charged particle concentrator (56) for collecting charged particles by an inner surface shape based on an ellipse;
A regenerative reducer (67E, 67l) having an electrode (71) electromagnetically coupled to the flow of charged particles, and a rectifier (67d +, 67d-);
The fusion-produced charged particles (49c) flying isotropically from the fusion reaction region (52) in a pulse form are converged by the charged-particle converging device (56), and the kinetic energy (49c) of the fusion-produced charged particles (49c) is reduced. K) is a simplified type (50s) that directly converts the electric power of the regenerative speed reducer (67E) to obtain DC electric energy (E) and decelerates charged particles.
It is characterized by comprising the charged particle concentrator (56), the regenerative speed reducer (67E, 67l) and the rectifier (67d +, 67d-).
The charged particle beam collision type fusion reactor (50) according to claim 1.
Fusion fuel of charged particle beam, one of which is slow and the other is fast,
What is deuterium (D) and helium ^{3 (3} He), and,
Are those helium ^{3 (3} He) to both,
An energy converter (67) that obtains the kinetic energy (K) of the fusion-producing particles,
A charged particle concentrator (56) for collecting charged particles by an inner surface shape based on an ellipse,
A regenerative reducer (67E, 67l) having an electrode (71) electromagnetically coupled to the flow of charged particles;
A resistor (67R) for converting electric energy (E) into heat energy (Q), and a heat exchange chamber (67Q);
The fusion-produced charged particles (49c) flying isotropically from the fusion reaction region (52) in a pulse form are converged by the charged-particle converging device (56), and the kinetic energy (49c) of the fusion-produced charged particles (49c) is reduced. K) is directly converted into electric power by the regenerative speed reducer (67E) to obtain electric energy (E), and at the same time, decelerates the charged particles and causes an electromagnetically induced current to flow through the resistor (67R) to generate thermal energy (Q). Is a heat conversion type (50h) that converts
The regenerative speed reducer (67E, 67l) and the resistor (67R) are provided.
A charged particle beam collision-type fusion reactor (50) according to any one of the preceding claims.
Fusion fuel of charged particle beam, one of which is slow and the other is fast,
Both are deuterium (D); and
Deuterium (D) and tritium (T)
The DD reaction and the DT reaction are performed in cooperation with each other, including those performed in an independent furnace, and those performed in one furnace,
The energy converter (67) for obtaining the kinetic energy (K) of the fusion-produced charged particles (49c)
A charged particle concentrator (56), a regenerative speed reducer (67E, 67l), and
A charged particle separator (68x) for separating charged particles for each nuclide by a charge-mass ratio (m / z) by passing through a fan-shaped magnetic field and an electric field, a fuel particle circulation path (69) for circulating tritium (T), And
A heat exchanger (67c) filled with a neutron moderator (10) and a heat exchange chamber (67s) composed of a neutron shielding chamber (67s) are provided to an energy converter (67) for acquiring kinetic energy (K) of neutrons (n). 67Q)
The fusion-produced charged particles (49c) flying isotropically from the fusion reaction region (52) in a pulse form are converged by the charged particle converging device (56), and the kinetic energy (K) of the charged particles is reduced by the regenerative deceleration. The electric power is directly converted by the heater (67E) to obtain the electric energy (E) (including the heat energy (Q) converted by the resistor (67R)), and the charged particles are decelerated.
Separation for each nuclide by the difference in the velocity (arrival time) of the fusion-produced charged particles (49c) and the difference in charge-mass ratio (m / z) by the charged particle separator (68x). Circulating tritium (T) in the form of charged particles to the associated DT reaction particle accelerator (62) by the circulation path (69);
The neutrons (n) flying in a pulsed isotropic manner from the fusion reaction region (52) are converted into thermal energy (Q) by the heat exchange chamber (67Q) and absorbed by the neutron moderator (10). Shield
It is a tritium annihilation cooperative type (50c) configured to immediately annihilate tritium (T).
A heat exchange chamber (67Q) including 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 having
The charged particle beam collision type fusion reactor (50) according to any one of claims 1 to 4.
Fusion fuel of charged particle beam, one of which is slow and the other is fast,
Both are deuterium (D); and
Deuterium (D) and tritium (T)
The DD reaction and the DT reaction are performed in cooperation with each other, including those performed in an independent furnace, and those performed in one furnace,
Heat exchange having a tritium breeding chamber (67T) filled with a tritium breeding material (including lithium (Li) and its compound) in an energy converter (67) for obtaining kinetic energy (K) of neutrons (n). Room (67Q), and
A mechanism for circulating helium 4 gas (24) to recover tritium (T), and a hydrogen separator (82) for separating hydrogen gas;
Receiving irradiation of neutrons (n) flying in a pulsed isotropic manner from the fusion reaction region (52), multiplying tritium (T) in the tritium breeding chamber (67T),
Helium 4 gas is circulated gas ⁽⁴ the He) circulating the hydrogen separator (82) by a gas containing tritium (T) was collected, the fuel particles circulating path for D-T reactor tritium (T) ( 69) is a tritium multiplication type (50t) having a configuration added to
A tritium breeding chamber (67T) having a tritium generation rate (η _t ) of less than 1;
The charged particle beam collision type fusion reactor (50) according to any one of claims 1 to 4.
Fusion fuel of charged particle beam, one of which is slow and the other is fast,
Deuterium (D) and tritium (T)
Tritium breeding into an energy converter (67) that obtains the kinetic energy (K) of neutrons (n), including those configured with a single DT reactor and those that link 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 circulating helium 4 gas (24) to recover tritium (T), a hydrogen separator (82) for separating hydrogen gas, and
A mechanism for adjusting the dose of neutrons (n) reaching the tritium breeding chamber (67T) (a neutron conditioning chamber (67v), a DT having a tritium generation rate (η _t ) of less than 1 or having no tritium breeding chamber (67T)) Neutron (n) flying in a pulsed isotropic manner from the fusion reaction region (52), and the neutrons (n) and tritium (T) are multiplied in the tritium breeding chamber (67T). And
Helium 4 gas is circulated gas ⁽⁴ the He) circulating a gas containing tritium (T) was collected by the hydrogen separator (82), and tritium (T) Fuel D-T reactor,
A tritium breeder (50T) having a mechanism for adjusting the dose of neutrons (n) reaching the tritium breeding chamber (67T);
A tritium breeding chamber (67T) having a tritium generation rate (η _t ) of more than 1;
The charged particle beam collision type fusion reactor (50) according to any one of claims 1 to 4.
Having a container made of a tough insulator material such as ceramics to prevent charged particles from directly contacting the electrode, and
An electrode (71) for removing charge is provided outside the insulator container, and a charge removal operation is performed by periodically applying a high voltage.
A particle accelerator (62) for accelerating charged particles serving as fuel,
A capillary (63c) for converging charged particles serving as fuel,
Charged particle converging device (56) for converging fusion-produced charged particles (49c),
A regenerative moderator (67E, including an ion orbiting moderator (67l)) for decelerating the fusion-produced charged particles (49c);
A charged particle separator (68x) for separating the fusion-produced charged particles (49c) based on a difference in mass-to-charge ratio (m / z);
An ion recovery path (68c) for recovering unreacted fuel particles (49n),
An ion transfer path (68) for transferring charged particles,
An ion flow bending device (68r) for changing the traveling direction of charged particles, and
It is provided with any one or more of ion neutralizers (70) which give electrons to charged particles and return them to gas.
A charged particle beam collision-type fusion reactor (50) according to any one of the preceding claims.
An ion flow bending device (68r) having a fan-shaped magnetic field (including a fan having a combined fan-shaped electric field of 68m and a fan-shaped electric field 68e) that bends charged particles that have entered, and has different mass-to-charge ratios (m / z). An ion flow bending device (68r) having an ion neutralizer (70) for separating and returning the particles to a gas.
A charged particle beam collision-type fusion reactor (50) according to any one of claims 1 to 7.