JPH07151879A - Cycling system of tritium fuel - Google Patents

Abstract

PURPOSE:To enhance economy by decreasing the amount of tritium produced from lithium and to alleviate the amount of the waste of the tritium and the radiation exposure on works and environments as a result. CONSTITUTION:A helium gas recovery system 16 and a helium gas circulating system 17 are connected, and the helium-gas circulating system 17 is connected to a blanket 6. Helium-3, which is a disintegrated product of tritium, generated in a tritium storing gas system 1 and a tritium-waste treatment system 13, is recovered by a helium-gas recovery system 16. Helium-4 (alpha-particle), which is generated by the nuclear fusion reaction of tritium conveyed through an exhaust-gas purifying system 8 and deuterium and the nuclear reaction of the lithium and neutrons, is recovered by the helium-gas recovery system 16. The helium-3 in the recovered helium gas is sent into a blanket 6 from the helium- gas circulating system 17. The helium-3 reacts with the blanket 6 around core plasma 5 and neutron, and tritium is reproduced and recovered.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a tritium fuel cycle system in a deuterium-tritium fusion reactor which is a fusion reactor using tritium as a part of fuel.

[0002]

2. Description of the Related Art Currently, the planned deuterium-tritium fusion reactor uses deuterium and tritium as fuels. Deuterium is a stable hydrogen isotope, and it exists in nature at a concentration of about 0.015%, and is industrially produced at deuterium production plants in other countries.

On the other hand, tritium is an unstable hydrogen isotope, and its natural abundance is extremely low, so that it is artificially produced by a nuclear reaction. The tritium for the fusion reactor fuel artificially produced by the nuclear reaction is treated as a tritium fuel cycle system as shown in FIG. 6 in the fusion reactor.

A conventional tritium fuel cycle system will be described below with reference to FIG. That is, in the conventional tritium fuel cycle, as shown in FIG. 6, a tritium gas storage system 1, a deuterium gas storage system 2, a mixed fuel adjustment system 3 that mixes these to prepare a fuel, and this mixed fuel. A fuel injection system 4 connected to the downstream side of the adjustment system 3 is provided.

A core plasma 5 that burns fuel connected to the fuel injection system 4, and a blanket 6 that amplifies neutrons generated from the core plasma 5, regenerates tritium by the neutrons, and decelerates the neutrons to generate heat. When,
An unburned fuel exhaust system 7 is provided for discharging the unburned fuel as exhaust gas.

An exhaust purification system 8 for purifying fuel from exhaust gas connected to the unburned fuel exhaust system 7, and a blanket 6
The sweep gas circulation system 9 that circulates the gas that recovers the tritium generated in the breeding material inside, the sweep gas purification system 10, the heat exchange system 11 that recovers the heat in the blanket 6, and the steps 12 A tritium waste treatment system 13 for treating the generated waste containing tritium is provided. The exhaust purification system 8 is connected to the isotope separation system 14.

In this conventional tritium fuel cycle system, the tritium gas storage system 1 is loaded with tritium which is artificially produced separately by the nuclear reaction between lithium and neutrons prior to the operation of the nuclear fusion reactor. The deuterium gas storage system 2 stores deuterium produced by isotope enrichment in the isotope separation system 14.

Next, in the mixed fuel adjusting system 3, tritium and deuterium are mixed at an appropriate ratio and pelletized as a fuel for a fusion reactor. The adjusted fuel is the fuel injection system 4
And is injected into the core plasma 5. In the core plasma 5, tritium and deuterium are burned by a fusion reaction,
Neutrons and α particles, which are helium-4 nuclei, are generated. About 1% of the injected fuel burns the injected fuel, and the unburned fuel is discharged through the unburned fuel exhaust system 7.

On the other hand, the neutrons produced by the combustion of the fuel are decelerated in the blanket 6 and release thermal energy.
The heat is carried out to the heat exchange system 11 by the coolant. The blanket 6 is composed of a neutron multiplier, a tritium breeding material, and a cooling material. A lithium-containing substance is used as the tritium breeding material. It produces tritium and alpha particles.

As the coolant, helium, water, liquid lithium or the like is used. Tritium generated in the breeding material is recovered by the sweep gas in the sweep gas circulation system 9 and purified by the sweep gas purification system 10, then a part is sent to the tritium gas storage system 1 and a part is mixed fuel adjustment system. Sent to 3.

The α-particles generated from the breeding material and the α-particles generated by combustion of the fuel lose energy and combine with nearby electrons to become helium-4, which is discharged together with the unburned fuel from the unburned fuel discharge system 7, It is sent to the exhaust gas purification system 8. In the exhaust gas purification system 8, fuel is collected and purified, part of the refined fuel is stored in the tritium gas storage system 1 and deuterium gas storage system 2, part is sent to the mixed fuel adjustment system 3, and part is the same. It is sent to the body separation system 14.

As described above, the conventional tritium fuel cycle system is a system in which neutrons generated by combustion of fuel and breeding material containing tritium generate tritium and supply it as fuel. That is, the amount of tritium consumed by the operation of the fusion reactor is newly supplied from the outside by using the breeding material.

By the way, tritium is not only consumed by the combustion of fuel, but also due to nuclear instability of tritium, the decay product, helium-3, has a half-life of about 12.3 years.
It is also reduced by β-decay. In addition, a part of tritium is transferred into the waste generated from each process 12 by the operation of the fusion reactor. The waste is in the form of gas, liquid or solid and is treated by the tritium waste treatment system 13.

As a waste treatment method, for example, a technology of diluting or stabilizing solidification of tritium drainage is in the development stage, but a disposal method including miscellaneous solid waste such as exchanged equipment is undecided. However, storage management is required until disposal measures are taken.

[0015]

In the conventional tritium fuel cycle system, in order to replenish the tritium consumed during the operation, it is necessary to separately supply the breeding material, and the replenishment of tritium causes a waste of tritium waste. There is a problem in that the amount of radiation is increased, and as a result, the radiation exposure of workers and the public is increased.

The present invention has been made to solve the above problems, and reduces the supply amount of breeding material and cooling material by effectively utilizing exhaust gas generated by combustion of fuel, storage of fuel, and the like. Increase economic efficiency and reduce tritium waste by reducing the amount of tritium supplied from the outside by reducing breeding materials, reducing waste treatment and management costs and reducing worker and public exposure. It is intended to provide a tritium fuel cycle system.

[0017]

The present invention is used in a fuel cycle system of a fusion reactor in which tritium is used as a part of fuel, and is a helium produced by nuclear decay of tritium.
3 and a helium gas recovery system for recovering an exhaust gas containing helium-4 produced by a fusion reaction of tritium and deuterium, and a helium-containing gas recovered by the helium gas recovery system for heat generation with a blanket of a fusion reactor. A helium gas circulation system that circulates an exchange system, and a helium-containing gas recovered by the helium gas recovery system is caused to function as a coolant of a fusion reactor from its refrigerant capacity, and helium-3 which is a component of helium gas and neutrons. It is characterized by comprising a system which functions as a breeding material for tritium by regenerating tritium by a nuclear reaction.

Further, the present invention is used in a fuel cycle system of a fusion reactor in which tritium is used as a part of fuel, and helium-3 produced by nuclear decay of tritium, a fusion reaction of tritium and deuterium, and lithium. Helium gas recovery means for recovering exhaust gas containing helium-4 generated by nuclear reaction with neutrons, and helium for circulating the helium-containing gas recovered by the helium gas recovery system through a breeder containing lithium and a heat exchange system A gas injection system and a system for causing the helium-containing gas recovered by the helium gas recovery system to function as a cooling material and a breeding material and also as a sweep gas for recovering tritium generated from lithium in the breeding material were provided. It is characterized by

[0019]

In the tritium fuel cycle system according to the present invention, the helium gas recovery system for recovering the exhaust gas containing helium causes the helium generated by β decay while the tritium stays in the tritium fuel cycle.
3, an exhaust gas containing helium-4 produced by a nuclear fusion reaction of deuterium as a fuel and tritium, and helium-4 produced by a nuclear reaction of neutrons contained in a breeding material or a coolant. Collect through.

The helium gas circulation system for circulating the helium-containing gas adjusts the temperature and pressure of the helium-containing gas, cools it, and sends it to the blanket. The helium-containing gas recovers the thermal energy of neutrons given to the blanket as a cooling material, and further produces tritium by a nuclear reaction between helium-3, which is one component of the helium-containing gas, as a breeding material and neutrons.

The tritium-containing gas that has recovered heat and produced tritium releases heat in the heat exchange system, and is sent to the helium gas recovery system again through the exhaust system and the exhaust purification system. Therefore, tritium can be regenerated by helium-3 contained in the exhaust gas, and the helium-containing gas itself can cool the fusion reactor.

[0022]

EXAMPLE An example of the tritium fuel cycle system according to the present invention will be described with reference to FIGS. 1 to 4. In the figure, the same parts as those in FIG. 6 are designated by the same reference numerals.
FIG. 1 shows the main configuration of the tritium fuel cycle system of this embodiment.

That is, in FIG. 1, the tritium and heavy of the tritium gas storage system 1 for storing tritium for fuel and the deuterium gas storage system 2 for storing deuterium for fuel, which are components of the tritium fuel cycle system, are shown. A mixed fuel adjusting system 3 that mixes hydrogen at an appropriate ratio, a fuel injection system 4 that injects the fuel mixed by this mixed fuel adjusting system into the core plasma 5, and the fuel is extracted from the core plasma 5 by burning the fuel. Heat exchange system that converts energy into heat 11
Are connected.

Further, a tritium waste treatment system 13 for treating radioactive waste containing tritium generated from each step 12 of the nuclear fusion plant is provided. Exhaust gas purification system 8 for producing tritium and deuterium from the exhaust gas emitted from the heat exchange system and tritium waste treatment system 13, and separation and selection of tritium and deuterium from the gas transferred from the exhaust gas purification system 8. It is equipped with an isotope separation system 14.

Further, a first exhaust system 15 for exhausting the atmospheric gas of the tritium gas storage system 1, and the first exhaust system 15
A helium gas recovery system 16 is provided for recovering the gas containing helium-3 discharged by the above and the helium-containing gas separated from tritium and deuterium in the exhaust purification system 8.

A helium gas circulation system 17 is provided for sending the helium-containing gas recovered by the helium gas recovery system 16 into the blanket 6 used as a cooling material and a breeding material for tritium.

The heat exchange system is circulated in the blanket 6.
A second exhaust system 18 for discharging the helium-containing gas, the unburned fuel gas in the core plasma 5 and the exhaust gas in the tritium waste treatment system 13 via 11 and sending them to the exhaust purification system 8 is connected.

Next, the operation of the tritium fuel cycle system having the above structure will be described. The tritium gas storage system 1 and the deuterium gas storage system 2 are initially loaded with a fuel gas produced separately before the operation of the fusion reactor is started. The required amounts of tritium and deuterium are transferred to the mixed fuel adjusting system 3 and pelletized. The adjusted pellet fuel is the fuel injection system 4
After being sent to the core plasma 5, it is injected into the core plasma 5 and the injection amount is 1
% Burns.

The unburned fuel remaining without being burned is exhausted by the second exhaust system 18 as exhaust gas by vacuum exhaust. The exhaust gas mainly contains tritium and deuterium gas, and also contains helium-4 produced by a nuclear fusion reaction of tritium and deuterium.

This mixed gas is transferred to the exhaust gas purification system 8 and separated into tritium, deuterium and other components. Part of the separated tritium and deuterium is sent to the tritium gas storage system 1 and the deuterium gas storage system 2, part is sent to the isotope separation system 14, and part is sent to the mixed fuel adjustment system 3. To be

The isotope separation system 14 performs isotope separation of tritium and deuterium, and the separated gases are sent to respective storage systems or mixed fuel adjusting systems. Helium-4 separated from tritium and deuterium in the exhaust purification system 8
The gas containing is recovered by the helium gas recovery system 16 described later.

On the other hand, the tritium stored in the tritium gas storage system 1 undergoes nuclear conversion into helium-3 with a half-life of about 12.3 years due to β decay. For example, about 5% of the amount of tritium stored for one year is converted to helium-3, and about 10% of tritium stored for two years is converted to helium-3. As described above, the helium-3 generated in the tritium gas storage system 1 is added to the first exhaust system together with the atmosphere gas of the storage system facility.
It is discharged by 15 to the helium gas recovery system 16 described later and recovered.

In the helium gas recovery system 16, the first exhaust system
The gas containing helium-3 sent through 15 and the gas containing helium-4 sent through the exhaust purification system 8 are mixed. The helium-containing gas is sent to the helium gas circulation system 17 after its temperature is adjusted by the cooler and its pressure is adjusted by the compressor. The helium-containing gas is sent to the blanket 6 and circulated, and then discharged through the heat exchange system 11 and the second exhaust system 18.

Next, the flow of the helium-containing gas from the helium gas circulation system 17 to the second exhaust system 18 will be described with reference to FIG. Helium gas recovery system 16 to helium gas circulation system 17
The helium-containing gas sent to is introduced into the helium gas circulation line 19. Helium gas circulation line 19
It is arranged at a position where it can circulate in the blanket 6, efficiently receive the neutrons amplified by the neutron multiplier 20, and efficiently recover the heat generated by the deceleration of the neutrons.

That is, in FIG. 2, the helium gas circulation line 19 circulates once around the neutron multiplier 20. However, for example, the helium gas circulation line 19 is in close contact with the neutron multiplier 20 or circulated several times in the neutron multiplier. By doing so, neutron irradiation efficiency and heat recovery efficiency can be improved.

While the helium-containing gas circulates in the blanket 6 through the helium gas circulation line 19, tritium is produced by a nuclear reaction between helium-3, which is a contained component, and neutrons, and the blanket is cooled. Since it is injected into 6, heat generated is efficiently recovered.

Subsequently, the helium gas circulation line 19 circulates in the heat exchange system 11 and releases the heat absorbed by the helium-containing gas in the blanket 6 to the heat exchanger 21 of the heat exchange system 11.
The helium-containing gas that has released heat is exhausted by the second exhaust system 18, and unburned fuel exhaust line 22 sends unburned tritium and deuterium to the second exhaust system 18, and
The temperature and pressure are adjusted and recycled along with helium-4 etc. generated by the combustion of fuel.

As is clear from the above description, according to the present embodiment, it is possible to recover helium-3 produced by β-decay of tritium and helium-4 produced by combustion of fuel.

While the recovered helium-containing gas is circulated in the blanket 6 and the heat exchange system 11 to cool and heat exchange the core, helium-3 is irradiated with neutrons to regenerate tritium. It is possible to replenish the tritium fuel in a closed system without newly using the breeding material and the cooling material.

By the way, in the tritium fuel cycle system of this embodiment shown in FIG. 1, when the content or concentration of helium-3 in the recovered helium-containing gas is low, the amount of tritium necessary for refueling cannot be obtained. There are cases.

In such a case, a helium-containing gas and a lithium-containing substance are used together as a tritium breeding material,
Moreover, a tritium fuel cycle system in which the helium-containing gas functions as a coolant and as a sweep gas for recovering tritium produced by the nuclear reaction of the lithium-containing substance and neutrons will be described with reference to FIG.

FIG. 3 shows an example of the flow of the helium-containing gas in the tritium fuel cycle system. The configuration from the second exhaust system 18 to the helium gas recovery system 16 is the same as that of the embodiment shown in FIG. 1, and the helium gas recovery system 16 and the subsequent devices supply the recovered helium-containing gas to the lithium-containing breeding material 23 of the blanket 6. To the helium gas injection system 24 and the helium gas injection line 25, and the regenerated tritium discharge line 26 that collects the helium-containing gas injected into the lithium-containing breeding material 23 and sends it to the second exhaust system 18 via the heat exchange system 11. It is composed of

Next, the operation of the tritium fuel cycle system of the example shown in FIG. 3 will be described. Blanket 6
Is a neutron multiplier 20 and a lithium-containing tritium breeder 23
It is composed of. The lithium-containing breeding material 23 contains lithium and is generated by the core plasma 5 and is a neutron multiplication material.
Tritium is produced by the nuclear reaction between neutrons amplified at 20 and lithium. The generated tritium is confined in the lithium-containing multiplier material 23.

The helium-containing gas recovered by the helium gas recovery system 16 is injected into the lithium-containing breeding material 23 by the helium gas injection system 24 through the helium gas injection line 25. Since helium gas can serve as a carrier for tritium, the helium-containing gas injected into the lithium multiplication material 23 is sent to the regenerated tritium discharge line 26 while sweeping the trapped tritium.

At this time, the helium-containing gas absorbs heat generated by decelerating neutrons in the lithium-containing breeding material 23, and the heat absorbed while the regenerated tritium discharge line 26 circulates in the heat exchange system 11. To release.

The helium-containing gas that has completed the heat exchange is sent to the second exhaust system 18, and unburned tritium also sent from the core plasma 5 to the second exhaust system 18 through the unburned fuel discharge line 22. After the temperature and pressure are adjusted together with deuterium and helium-4 generated in the fusion reaction, they are recycled.

As is clear from the above description, according to the example of FIG. 3, the amount of tritium produced from helium-3 contained in the recovered helium-containing gas can be supplemented with tritium produced by the reaction of lithium and neutrons. .

Further, although the lithium-containing substance is used as a part of the breeding material as in the conventional tritium fuel cycle system shown in FIG. 6, in the embodiment of the present invention, tritium can be regenerated from the helium-containing gas. In addition, the amount of the lithium-containing substance used can be reduced as compared with the conventional one.

Furthermore, the tritium retained in the lithium breeder can be swept by the helium-containing gas, and the helium-containing gas absorbs the heat generated by the deceleration of neutrons in the lithium breeder and releases it in the heat exchanger. Therefore, the helium-containing gas can be used as the sweep gas of the regenerated tritium and can also function as a coolant.

Next, in the embodiments of the present invention described so far, the recovered helium-containing gas is sent to the helium gas circulation system 17 or the helium gas injection system 24 by adjusting the temperature and pressure, but the required amount of tritium is required. In order to obtain the above, a system for increasing the helium content ratio in the helium-containing gas in the helium gas recovery system 16, that is, a helium enrichment system will be described with reference to FIG.

FIG. 4 shows an example of a helium enrichment system in the tritium fuel cycle system of the embodiment shown in FIG. 1, in which the helium gas recovery system 16 includes a pressure regulator 27 and a first compressor 28. A drier 29, a helium rough purification column 31 equipped with a helium selective permeable membrane 30, a chiller 33 for cooling a liquefied impure gas 34 from a first cooling device 32, and a second cooling device 35. Multiple adsorption towers 36 and exhaust / drainage system
Composed of 37 and.

The exhaust / drainage system 37 is a tritium waste treatment system.
13, the first exhaust system 15 is connected to the pressure regulator 27,
The second compressor 38 is connected to the helium gas circulation system / injection system 17, 24.

The operation of the helium enrichment system in the tritium fuel cycle system having the above structure will be described. To the helium gas recovery system 16, helium, atmospheric gas mixed from each system, and some leaked tritium and deuterium are transferred by the first exhaust system 39. The transferred exhaust gas is mixed in the pressure regulator 27 and adjusted to a constant pressure as a whole. The mixed gas, helium-containing gas, is first compressed by the first compressor 28 to reduce its volume, and then dried.
The moisture is removed by drying at 29.

Next, the dried helium mixed gas is guided to the helium rough purification column 31, and is helium is roughly concentrated by passing it through the helium selective permeable membrane 30 which is permeable to helium and impermeable to other gases.

Subsequently, the crudely concentrated helium-containing gas is sent to the deep cooling tower 33. The chilling tower 33 is temperature-controlled by the first cooler 32 that cools to a cryogenic temperature higher than the liquefying temperature of helium, and most of the gas other than helium (called impure gas) is condensed and liquefied impure gas. Cryogenic tower as 34 33
A small amount of impure gas and helium that have accumulated in the lower part of the column and have not been liquefied are sent to the adsorption tower 36 as non-condensed gas.

The adsorption tower 36 is loaded with an adsorbent for adsorbing the impure gas, and the impure gas is adsorbed and separated by aeration of the non-condensable gas while the adsorption tower 36 is cooled by the second cooler 35. . Therefore, the helium-containing gas discharged from the adsorption tower 36 has a high helium concentration, is recompressed by the second compressor 38, and is sent to the helium gas circulation system 17 or the helium gas injection system 24.

In the helium rough purification tower 31, the impure gas separated in 31 and the adsorption tower 36 and the liquefied impure gas 34 separated in the chilling tower 33 are collected by the exhaust / drainage system 37 and collected in the tritium waste treatment system 13. It is processed.

In the example shown in FIG. 4, a gas other than helium is separated and discharged by combining the helium crude refining tower 31, the chilling tower 33 and the adsorption tower 36 as means for increasing the helium concentration. When the degree of purification, that is, the degree of enrichment, of helium is low, it is possible to use a combination of two means out of these three means or one means alone. Further, each means can be assembled in a plurality of stages in order to further enhance the enrichment.

As is clear from the above description, according to the example shown in FIG. 4, helium in the helium-containing gas is enriched with helium by membrane separation, cryogenic separation or adsorption separation. When applied to a tritium fuel cycle system that uses a helium-containing gas as a breeding material as shown in FIG.
The degree of recovery can be increased.

When applied to a tritium fuel cycle system using both a helium-containing gas and a lithium-containing substance as breeding materials as shown in FIG.
It is possible to increase the recovery and reduce the amount of the lithium-containing substance.

Next, another embodiment of the present invention will be described with reference to FIG. In FIG. 5, the same parts as those in FIG. 1 are designated by the same reference numerals, and the description of the overlapping parts will be omitted.

A third exhaust system for exhausting the exhaust gas sent from the refined exhaust system 8, a helium mixed gas recovery system 40 for recovering the helium-containing gas exhausted by the third exhaust system 39, A helium-3 gas recovery system 41 for recovering the exhaust gas of the tritium gas storage system 1 exhausted by the exhaust system 15 of No. 1, a helium-3 purification system 42 for purifying helium-3 in the exhaust gas, and a purification Helium-3 extraction system 43 for extracting the generated helium-3 gas, and helium-3
A gas mixing system 44 is installed which mixes the gases recovered by the three-gas recovery system 41 and the helium mixed gas recovery system 40 and sends them to the helium gas circulation system 17.

The exhaust gas of the tritium gas storage system 1 contains helium-3, which is a decomposition product of tritium, but helium-4 is extremely small if mixed from other systems. , Helium-3 has a much higher isotope ratio than helium-4. Only this gas is recovered by the helium-3 gas recovery system 41 through the first exhaust system 15.

On the other hand, the helium in the exhaust gas recovered from the exhaust purification system 8 through the third exhaust system 39 to the helium mixed gas recovery system 40 is stored in the helium-4 produced in the fusion reaction and in the blanket 6. It contains both neutron and helium-3 isotopes that did not undergo nuclear reaction.

Therefore, the helium-containing gas having a high isotope ratio of helium-3 recovered by the helium-3 gas recovery system 41 is mixed with the gas recovered by the helium mixed gas recovery system 40 by the gas mixing system 44, and the temperature is changed. After the pressure is adjusted, the helium gas circulation system 17 sends the blanket 6 to the blanket 6 to obtain the same effects as those of the embodiments described above.

Further, in the helium-3 gas purification system 42, the helium gas having a high helium-3 isotope ratio is separated and purified from the impure gas by, for example, cryogenic separation, and the pressure is adjusted to obtain the purified helium-3 gas extraction. By storing in the system 43, a highly purified helium-3 source can be obtained.

[0067]

According to the present invention, a lithium-containing breeding material, which is a material for replenishing tritium, is provided with means for recovering helium contained in exhaust gas and recycling the recovered helium-containing gas. Reduce the amount,
Or, it can provide an economical system that does not require new supply.

Further, since the amount of tritium supplied from the outside is reduced, it is possible to reduce the amount of tritium exhaust gas, thereby reducing the waste treatment and management costs and reducing the radiation exposure of workers and the public. Become.

[Brief description of drawings]

FIG. 1 is a block diagram showing an embodiment of a tritium fuel cycle system according to the present invention.

FIG. 2 is a block diagram showing a flow of a helium-containing gas according to an embodiment of the present invention.

FIG. 3 is a block diagram showing a flow of a helium-containing gas according to an embodiment of the present invention.

FIG. 4 is a block diagram showing the configuration of a helium gas recovery system in one embodiment of the present invention.

FIG. 5 is a block diagram showing the configuration of a tritium fuel cycle system according to another embodiment of the present invention.

FIG. 6 is a block diagram showing a conventional tritium fuel cycle system.

[Explanation of symbols]

1 ... Tritium gas storage system, 2 ... Deuterium gas storage system, 3
... mixed fuel adjusting system, 4 ... fuel injection system, 5 ... core plasma, 6 ... blanket, 7 ... unburned fuel exhaust system, 8 ... exhaust purification system, 9 ... sweep gas circulation system, 10 ... sweep gas purification system, 11 ... Heat exchange system, 12 ... Each process, 13 ... Tritium waste treatment system, 14 ... Isotope separation system, 15 ... First exhaust system, 16 ... Helium gas recovery system, 17 ... Helium gas circulation system, 18 ... 2 exhaust system, 19 ... Helium gas circulation line,
20 ... Neutron multiplier, 21 ... Heat exchanger, 22 ... Unburned fuel exhaust line, 23 ... Lithium-containing breeder, 24 ... Helium gas injection system, 25 ... Helium gas injection line, 26 ... Regenerated tritium discharge line, 27 … Pressure regulator, 28… First compressor, 29
... dryer, 30 ... helium selective permeable membrane, 31 ... helium rough purification tower, 32 ... first cooling device, 33 ... chiller, 34 ... liquefied impure gas, 35 ... second cooling device, 36 ... adsorption tower , 37 ... Exhaust / drainage system, 38 ... Second compressor, 39 ... Third exhaust system, 40 ... Helium mixed gas recovery system, 41 ... Helium-3 gas recovery system, 42
... Helium-3 purification system, 43 ... Purification helium-3 gas extraction system.

Claims (3)

[Claims] 1. A helium-3 that is used in a fuel cycle system of a fusion reactor that uses tritium as a part of fuel, and that is produced by the nuclear decay of tritium, and a helium-4 that is produced by the fusion reaction of tritium and deuterium. A helium gas recovery system for recovering exhaust gas including and a helium gas circulation system for circulating the helium-containing gas recovered by the helium gas recovery system through the blanket and heat exchange system of the fusion reactor, and the helium gas recovery system. The recovered helium-containing gas is made to function as a coolant for the fusion reactor due to its refrigerant capacity,
A tritium fuel cycle system comprising: a system that functions as a breeding material for tritium by regenerating tritium by a nuclear reaction between helium-3, which is a component of helium gas, and neutrons. 2. A helium-3, which is used in a fuel cycle system of a nuclear fusion reactor that uses tritium as a part of fuel, and is produced by nuclear decay of tritium, a fusion reaction of tritium and deuterium, and lithium and neutrons. Helium gas recovery means for recovering exhaust gas containing helium-4 produced by nuclear reaction, and helium gas injection system for circulating the helium-containing gas recovered by the helium gas recovery system through a breeder containing lithium and a heat exchange system And a system that causes the helium-containing gas recovered by the helium gas recovery system to function as a coolant and a breeding material, and also function as a sweep gas that recovers tritium generated from lithium in the breeding material. And tritium fuel cycle system. 3. The helium gas recovery system membrane-separates helium gas and other gas from the recovered helium-containing gas,
3. The tritium fuel cycle system according to claim 1 or 2, wherein helium is enriched by separating by a combination of cryogenic separation and adsorption separation or a single treatment.