JP2002080858A - Radiation-irradiated coal liquefaction plant - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a radiation-irradiated coal liquefaction plant which can efficiently liquefy coal at a high safeness while using excess thermal neutron produced in a nuclear reactor as a heat source and can accomplish the load leveling of a nuclear power generation system. SOLUTION: This plant is equipped with a nuclear power generation system 1 having a thermal neutron irradiation apparatus 8 which is arranged in a pressure container or a screening body of a nuclear reactor 5 generating steam for driving a power generation turbine or a high-temperature high-pressure gas and which forms an artificial radioactive isotope from a radioactive isotope- forming material by the irradiation with thermal neutron; a coal slurry preparation section 2 for preparing a coal slurry by mixing the above-formed artificial radioactive isotope with a coal powder, a solvent, and a catalyst; and a coal liquefaction system 3 for heating, liquefying, and decomposing the coal slurry prepared by the coal slurry preparation section and for separating the resultant decomposition product.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

The present invention relates to an artificial radioisotope having a short half-life produced from a natural element or an isotope-separated element by abundant and inexpensive thermal neutrons generated in a nuclear power generation system. The present invention relates to an irradiation coal liquefaction plant for adding coal to a coal liquefaction slurry to liquefy coal.

[0002]

2. Description of the Related Art In recent years, economic development has been supported by personal consumption such as the enlargement of home appliances and the spread of air conditioning, and the demand for electric power has been steadily increasing for both industrial and consumer use. . Since the growth of the maximum demand power is remarkable and exceeds the growth of the generated power amount, the power demand peaks, and the demand difference between seasons and day and night is increasing. For example, the power demand gap between day and night has reached about 40% of the maximum demand, and as a means of improving the load factor, pumped-storage power generation, power storage technologies such as superconductivity, flywheel, and air compression have been developed. .

[0003] Here, the storage energy efficiency of pumped storage power generation is about 70%, but there are problems such as restrictions on location points and a long construction period. On the other hand, among the power storage methods, when superconductivity or flywheel is used, there is a problem that it is not suitable for large capacity.

[0004] Measures for leveling the load in the power generation system and
Instead of responding with energy storage
Studying development / exploration that uses electric power, heat, etc. in new fields
Have been. For example, as one method of coal liquefaction,
Release into coal slurry containing coal powder, solvent and catalyst
After irradiating with radiation, under high temperature and high pressure conditions in a reducing gas atmosphere
It is reported that coal liquefaction is carried out in
59371, JP-A-6-287567). In addition, here
Now, as a radiation source, long half-life⁶⁰Co, ⁹⁰Sr
Since gamma rays are used, handling is inconvenient.

[0005] Incidentally, a nuclear power plant is operated at a 24 hour rating because the operation itself is low cost.
Low nighttime power demand results in surplus power, while thermal neutrons generated by the reactor surplus.
The present inventors have studied the use of the surplus thermal neutrons to directly irradiate coal fine powder to perform coal liquefaction. However, bringing a large amount of combustible coal powder into a nuclear power plant poses a problem in terms of ensuring safety.

[0006]

As described above, a nuclear power plant has a lower fuel cost and a lower total power generation cost than a fossil fuel-fired power plant. On the other hand, on the other hand, there is a problem of thermal neutrons, which are sources of excess thermal energy, in addition to a problem of storage for leveling load of electric power.

Therefore, when utilizing this thermal neutron for coal liquefaction, an artificial radioisotope that emits β rays that is easy to shield and easy to handle is produced (manufactured).
When using radioisotopes that emit radiation, β-rays should be mixed directly with coal powder for irradiation because of short transmission distance, and the amount of radioactivity in the product after coal liquefaction should be below the natural radioactivity level. In order to achieve this, we have studied the use of artificial radioisotopes having a short half-life of several minutes to several hours.

The present invention has been made based on the results of the above-mentioned studies, and it is possible to liquefy coal efficiently with high safety by using excess thermal neutrons generated in a nuclear reactor as an energy source. An object of the present invention is to provide a radiation liquefied coal liquefaction plant capable of achieving load leveling of a power generation system.

[0009]

According to the first aspect of the present invention, thermal neutrons are disposed in a pressure vessel or inside a shield of a nuclear reactor for generating steam for driving a power generation turbine or high-temperature and high-pressure gas. A nuclear power generation system having a thermal neutron irradiation device for generating an artificial radioisotope from a material for radioisotope generation, and a coal slurry for preparing a coal slurry by mixing the generated artificial radioisotope with coal powder, a solvent and a catalyst The configuration includes a preparation unit and a coal liquefaction system that heats, liquefies and decomposes the coal slurry prepared by the coal slurry preparation unit, and separates decomposition products.

According to the present invention, the use of thermal neutrons generated in a nuclear reactor produces an artificial radioisotope which undergoes β decay having a relatively short half-life. In addition, by using the generated artificial radioisotope in the pre-treatment of the coal liquefaction reaction, β-rays and γ-rays effectively relax the coal structure, and the hydrogenolysis in the subsequent liquefaction reaction is performed with high efficiency. Can be achieved. Here, achieving a desired high liquefied oil yield even under low-temperature and low-pressure conditions leads to a reduction in the construction cost of a coal liquefaction apparatus or a reduction in coal liquefaction cost.

[0011] Further, since a configuration is adopted in which artificial radioisotopes are produced around the reactor and supplied to the adjacent coal liquefaction system, safety and safety can be achieved without bringing a large amount of combustible materials directly into the nuclear power generation system. It can be said that the coal liquefaction system is advantageous even at low cost.

The thermal neutron irradiation device is installed in the core region with the same outer shape as the core fuel of the nuclear power generation system, installed inside the shroud in the reactor pressure vessel, or installed outside the reactor pressure vessel. And, in the case of a nuclear reactor that generates high-temperature and high-pressure gas for rotation of the reactor turbine, is installed inside the shielding layer, or is installed outside the pressure vessel, or the movable reflector area in the reactor pressure vessel or Place in the fixed reflector area.

According to a second aspect of the present invention, at least one of Al, Si, Ti, V and Mn is used as the material for generating radioisotopes. ADVANTAGE OF THE INVENTION According to this invention, the half-life of radioactivity can produce | generate the artificial radioisotope which performs beta decay of several minutes to several hours.

According to a third aspect of the present invention, the material for producing a radioisotope is ³⁰ Si, ⁵⁰ Ti, ⁵⁴ Cr, ⁶⁴ Ni,
^The structure is at least one of ⁶⁵ Cu and ⁶⁸ Zn. ADVANTAGE OF THE INVENTION According to this invention, the production efficiency of an artificial radioisotope improves remarkably compared with the case of a natural element.

It is preferable to use an isotope separation system using a visible light pulse laser for the isotope separation. This isotope separation system using a visible light pulse laser uses a visible light pulse laser to evaporate the separated material and irradiate it with a visible pulse laser before ejecting the separated material from a nozzle to selectively excite or multi-step excitation. In this method, ionized ions are ejected from a nozzle, the separated material ejected from the nozzle is irradiated with an electron shower to be ionized, and the separated material is separated into large cluster particles and single particles by an electrode and collected.

According to a fourth aspect of the present invention, the irradiation time of the thermal neutron on the material for generating a radioisotope is about the half-life of the artificial radioactive element to be generated, and is 1/10 or less of the half-life after the irradiation of the thermal neutron. It is configured to be used for coal slurry preparation within time. According to the present invention, the artificial radioactive isotope described above can be effectively generated, and can be effectively applied to lime liquefaction decomposition.

According to a fifth aspect of the present invention, a carbon carrier is filled with fine particles of a material for generating radioisotopes and guided to a thermal neutron irradiator, and the carrier delivered from the thermal neutron irradiator is transported at high speed by gas. To the coal slurry preparation section.

According to the present invention, the operability of the artificial radioisotope fine particles is improved, and the transport speed inside and outside the thermal neutron irradiation device can be changed. High-speed transfer to the unit.

According to a sixth aspect of the present invention, there is provided a structure in which a crushing device for crushing a carrier and an separating device for guiding only fine particles of a radioisotope generating material to a coal slurry preparation tank are provided at the entrance side of the coal slurry preparation section. And

According to the present invention, it is possible to mix only the fine particles of the artificial radioactive element into the coal slurry and to irradiate the coal slurry effectively with radiation (β-ray). Can be separated.

According to a seventh aspect of the present invention, the fine particles of the radioisotope generating material filled in the carbon carrier have a ferromagnetic film on the surface. ADVANTAGE OF THE INVENTION According to this invention, the fine particles of an artificial radioisotope are recovered from coal slurry using a magnetic action, and an expensive artificial radioisotope material can be effectively reused. Note that nickel or iron is used as the ferromagnetic material.

An eighth aspect of the present invention is directed to a mixed medium system for cooling the exhaust or bleed air of a steam turbine of a nuclear power generation system, a refrigerant manufacturing system for manufacturing a refrigerant from a medium separated by the mixed medium system, and a heat generation of a compressor. A refrigerated carbon dioxide / oxygen liquefaction system for producing liquid carbon dioxide and liquid oxygen by removing the above with the refrigerant, a generated gas power generation system using a decomposition gas of a coal slurry as a fuel or a decomposition gas of a residue of a coal slurry as a fuel And at least one of the residue gasification power generation systems described above.

According to the present invention, by efficiently recovering the heat generated in the nuclear reactor to a low temperature, and by efficiently producing cold heat, the liquefied storage of oxygen can be efficiently performed by nuclear energy at night, Effective recovery of carbon dioxide can be achieved, and an environmentally friendly load leveling nuclear power system can be obtained at the same time.

According to a ninth aspect of the present invention, there is provided a coal slurry preparation tank for preparing a coal slurry by mixing coal powder, a solvent and a catalyst, and a pressure vessel of a nuclear reactor for generating steam or high-temperature high-pressure gas for driving a power generation turbine. And a circulation pipe provided between the shield or the wall of the primary biological shield and partially irradiating the coal slurry in the coal slurry preparation tank with radiation. ADVANTAGE OF THE INVENTION According to this invention, the equipment for manufacturing an artificial radioisotope, the radiation irradiation equipment using the same, etc. become unnecessary, and a system configuration becomes simple.

That is, in each of the above-mentioned inventions, an artificial radioisotope having a short half-life is generated by using thermal neutrons generated in a nuclear reactor, and the artificial radioisotope is utilized in a coal liquefaction system to improve the coal liquefaction efficiency. And the load leveling of the nuclear power generation system can be achieved. In the case of producing an artificial radioisotope with a short half-life of several minutes to several hours by irradiating thermal neutrons, please refer to the “Isotope Handbook” (edited by Japan Radioisotope Association, Maruzen) See “Appendix 1 Isotope Table, Decay Diagram”.

In the case of coal liquefaction, it is advantageous to make the particle size of the fine coal powder on the order of μm in order to increase the liquefaction yield while keeping the hydrogen consumption low, and it is advantageous to use a rod mill, a ball mill, a vibrating mill. After performing preliminary grinding with a disc mill or the like, the slurry is manufactured by a mechanical grinding method using a slurry jet mill. Here, as a driving source for mechanical pulverization, there is a means for directly converting electric power and heat energy into mechanical energy, and using heat energy is advantageous because energy conversion efficiency is improved. For example,
By using the thermal energy generated by the nuclear power generation system to generate cold heat, bringing the coal powder to a temperature below low-temperature brittleness, and irradiating with a shock wave generated when the combustion gas is pulsed, ultra-fine powder of coal is instantaneously produced. can get.

As a means for pulverizing coal, a shock wave generated when a mixed gas of natural gas and air is explosively burned at a high temperature (pulse burning) is used to process or evaporate. Examples of such a method include a method of applying a shock wave (impact pressure of about 100,000 atmospheres) generated by pulse combustion to a substance heated to a temperature lower than low-temperature brittleness using liquid nitrogen to instantaneously pulverize the substance. Here, in the case of means using liquid nitrogen, since the atmosphere is nitrogen gas, there is an advantage that dust explosion can be prevented at the same time.

[0028]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of the present invention will be described with reference to FIGS. 1 to 3. FIG. As shown in FIG. 1, the irradiated coal liquefaction plant of this embodiment includes a nuclear power generation system 1, a slurry preparation unit 2, a coal liquefaction system 3, and a product storage unit 4 as large components. Incorporating a thermal neutron irradiation device inside the shroud in the reactor pressure vessel of the nuclear power generation system 1, and having a surface coating of nickel on the thermal neutron irradiation device via a nozzle hole provided in the body of the reactor pressure vessel Aluminum (Al), silicon (S
i), a carrier made of carbon containing fine particles such as titanium (Ti), vanadium (V), and manganese (Mn) is supplied by airflow, and irradiated with thermal neutrons to generate artificial radioactive elements. An artificial radioactive element with a short half-life is mixed with fine coal particles, a solvent, a catalyst, etc., and the coal is liquefied at high temperature and high pressure.

In FIG. 1, reference numeral 1 denotes a nuclear power generation system, reference numeral 5 denotes a nuclear reactor for generating steam used for rotating a steam turbine 6 for power generation, and reference numeral 7 denotes a reactor for condensing steam used for the power generation. A condenser 8 to return to 5 is a thermal neutron irradiation device arranged inside or outside the pressure vessel of the reactor 5. In the thermal neutron irradiation device 8, the carrier gas stored in the carrier gas storage tank 9 is pressurized by the compressor 10a and supplied to the carrier supplying device 48 to contain the fine particles of the material for artificial radioisotope generation. The transporter 49 is transferred, and the carrier 49 is irradiated with thermal neutrons in the thermal neutron irradiation device 8 to generate artificial radioisotope fine particles from the fine particles of the artificial radioisotope generation material contained therein.

In this embodiment, as shown in a partially enlarged view in FIG. 2, the thermal neutron irradiation device 8 has a configuration in which it is incorporated in a part of a shroud 5b in a pressure vessel 5a of a nuclear reactor 5. I have. The conveying pipe for the artificial radioisotope generation material to the thermal neutron irradiation device 8 is connected via a nozzle hole 5g in the trunk of the reactor pressure vessel 5a. Note that FIG.
5c is a shield, 5d is a containment vessel, 5e
Is an isolation valve, and 5f is an internal pump.

Returning to FIG. 1, reference numeral 2 denotes a slurry preparing unit, which crushes a carbon carrier by a freezing and crushing device 33 and generates artificial radioactive isotope fine particles generated by the thermal neutron irradiation device 8 from the carrier. The removed fine particles and coal powder storage tank
There is provided a slurry preparation tank 14 for preparing a coal slurry by mixing with coal powder supplied from 11, a solvent supplied from a solvent storage tank 12, and a catalyst supplied from a catalyst storage tank 13. The coal slurry prepared in the slurry preparation tank 14 is supplied to a circulation pump 10b, a valve 10f, and a magnetic separator.
It is configured to be supplied to the coal liquefaction system 3 side via the pressure pump 47 and the pressure pump 10c. In the magnetic separator 47, artificial radioactive isotope fine particles having a surface coated with nickel from coal slurry are separated and recovered by using a magnetic effect.

The coal liquefaction system 3 includes a slurry preparation unit 2
A hydrogen storage tank 15 for supplying hydrogen to the coal slurry supplied from is provided, a heater 16 for heating the coal slurry as the object containing the hydrogen, a liquefaction reactor 17 for performing a decomposition / liquefaction reaction, and A reaction product separation device (high temperature separator) 18 for separating the decomposition / liquefaction reaction product by the liquefaction reaction device 17; The heater 16 is, for example, an induction helical coil.

Then, the first separated component consisting of gas and oil separated in the reaction product separation device 18 is fractionated in a first distillation column 19 for normal pressure distillation. The configuration is such that the product gas fractionated in the above is led to the product gas storage tank 20, the light medium oil is led to the light medium oil storage tank 21, and the water is led to the water storage tank 22, respectively. On the other hand, the second separation component including the residue component separated by the reaction product separation device 18 is fractionated in a second distillation column 23 for performing vacuum distillation, and the residue component is separated into a residue component tank 24.
Then, the evaporation component (solvent component) is sent to the hydrogenation reaction tank 25 via the circulation pump 10e, where it is hydrogenated and supplied to the solvent storage tank 12.

The operation of the irradiated coal liquefaction plant according to the present embodiment having the above-described configuration is as follows. First, in the nuclear power generation system 1, a coolant made of light water is heated in the reactor 5, becomes saturated steam, and is sent to the steam turbine 6 via the main steam pipe. The steam sent to the steam turbine 6 rotates and drives the steam turbine 6, and the rotating energy of the steam turbine 6 is converted into electric energy in a power generator to generate power. The exhaust gas (or bleed air) from the steam turbine 6 exchanges heat with the seawater flowing through the heat exchange section in the condenser 7 via an exhaust pipe to become condensed water. Reflux to 5.

On the other hand, the carrier gas in the carrier gas storage tank 9 is pressurized by the compressor 10a to the thermal neutron irradiation device 8 which forms a part of the shroud 5b in the pressure vessel 5a of the nuclear reactor 5, and the material for radioisotope generation is produced. Al, Si, T as
A carrier 49 made of carbon, which is made of a natural metal such as i, V, and Mn and contains fine particles having a nickel coating on its surface, is transferred from a carrier supplying device 48. Here, the thermal neutron irradiation device 8
In the above, when the transported carrier is irradiated with a thermal neutron flux of 10 ¹² / cm ² · s, the Al, Si, Ti, V or Mn becomes ²⁸ Al, ³¹ Si, ⁵¹ Ti, ⁵² V or ⁵⁶ M
nuclide conversion to n. Here, in the process of producing artificial radioisotopes by irradiating thermal neutrons, Ti and V that have not been converted into nuclides act as catalysts when sent to the slurry preparation tank 14.

[0036] Note that these nuclides converted nuclides half life 2.3 minutes ⁽²⁸ Al), 2.6 hours ⁽³¹ Si), 5.8 min ⁽⁵¹
Ti) for 3.8 minutes ( ⁵² V) or 2.6 hours ( ⁵⁶ Mn)
Since each β ^- decay is performed, the irradiation time of the thermal neutrons in the thermal neutron irradiation device 8 is set to a length of about half-life of the generated nuclide. The generated nuclides are transferred from the thermal neutron irradiation device 8 to the slurry preparation tank 14 within a period of about 1/10 to about a half life of the respective nuclides.

That is, as shown in FIG. 3, a carbon carrier 49 containing fine particles of an artificial radioisotope generating material is loaded between the valve 5h and the isolation valve 5e, and the thermal neutron irradiation unit 8 heats the carrier. The neutron irradiation is performed for a predetermined time. Before the irradiation of the thermal neutrons, the carrier 49 is loaded into the carrier supplying device 48. When the irradiation of the thermal neutrons is completed, the isolation valves 5e and 5h are opened, and the carrier gas is supplied by pressurizing the carrier gas with the compressor 10a. Supply to device 48. The valve 50 is also opened to inject the carrier gas. The pressure of the carrier gas branched to the valve 50 is set so that a pressure loss slightly larger than the pressure loss of the carrier gas passing through the valve 5h is generated by the valve 50 or the like.

The radiation amount of the carrier 49 is measured by the radiation detectors 5j and 5k, and the switching valve 5i is switched after a certain period of time when the radiation is detected by the radiation detector 5k, and the slurry is supplied from the pipeline to the carrier gas storage tank 9. A pipeline is provided to the preparation tank 14 so that the carrier 49 irradiated with thermal neutrons is transferred to the slurry preparation tank 14.

The radiation detector 5j measures the amount of radiation of the carrier 49 passing therethrough.
h, Close the isolation valve 5e. The radiation detector 5k measures the radiation amount of the carrier 49 passing therethrough. When the radiation amount is no longer detected, the switching valve 5i is switched after a certain period of time to transfer the carrier gas from the pipeline to the slurry preparation tank 14. Storage tank 9
And the valve 52 is opened.

When the carrier 49 disappears after the valve 5h, the valve 50,
The pressurization in the compressor 10a is stopped by closing 51 and 52. Thereafter, a route through which the carrier gas is discharged from the valve 5h and the isolation valve 5e to the carrier gas storage tank 9 so that the pressure between the valve 5h and the isolation valve 5e via the thermal neutron irradiation device 8 does not increase during the thermal neutron irradiation period. (Not shown, a heat removal mechanism is provided in the middle).

The interval of the transfer of the radioisotope is every time when the time for irradiating the coal slurry with β ^- rays or γ-rays in the slurry preparation tank 14 (length about half-life of the generated nuclide) is completed. .

The slurry preparation section 2 stores coal powder.
Raw coal powder supplied from storage tank 11, from solvent storage tank 12
Circulating solvent for coal liquefaction supplied, supplied from catalyst storage tank 13
A catalyst for increasing the yield of supplied liquefied oil;
Exchanged artificial radioisotopes ²⁸Al,³¹Si,⁵¹Ti,
⁵²V,⁵⁶Mn of each ton of coal slurry,
0.66kg, 110kg, 2.5kg, 0.068kg, 0.036kg
Into the rally preparation tank 14 and a certain atmosphere, pressure and
Mixing with internal stirrer while maintaining temperature and temperature conditions
Then, a coal slurry of a certain concentration is produced. Also heat neutral
Transported from the carbon irradiator 8 to the cryogenic crusher 33
Impact is applied to the transmitter 49 after injecting liquid nitrogen etc.
Crushed 49 to remove artificial radioisotope fine particles from inside
And only the fine particles are sent to the coal slurry preparation tank 14.
You.

The raw coal used here is obtained by drying 5 to 30% by weight of water contained in the coal to 1 to 2% by weight and pulverizing the coal particles to a particle size of 150 μm or less. . Further, as the solvent, it is desirable to use an oil having a hydrogen-donating ability, for example, an oil having a high content of aromatic components such as tetralin and tetrahydroanthracene, and is obtained by hydrogenating heavy oil obtained by coal liquefaction. Coal-based solvents (including tetralin) are preferred.

The catalyst is not particularly limited, but examples of metal species having catalytic activity include iron (Fe), nickel (Ni), molybdenum (Mo), titanium (Ti), vanadium (V), and lanthanum (La). However, iron (Fe) and nickel (Ni) are inexpensive and readily available, and have a large catalytic effect in the coal liquefaction. As the iron-based catalyst, a synthetic iron sulfide catalyst, iron hydroxide or a natural iron ore catalyst can also be used. In any case, use a catalyst with a particle size of 16 μm or less
% Is preferable.

In the preparation in the slurry preparation tank 14, the concentration of the coal slurry was about 1.0 to 4.0 in terms of the solvent weight ratio (solvent / raw coal) to the dry weight of the raw coal, and the amount of catalyst added was 0.5 to dry weight of particles
It is about 5% by weight. The atmosphere in the slurry preparation tank 14 is an inert gas atmosphere, the temperature is about 40 to 100 ° C., and the pressure is about 1 to 10 atm.

Coal mixed and prepared in the slurry preparation tank 14
The slurry contains artificial radioisotopes ( ²⁸Al,³¹Si,⁵¹
Ti,⁵²V,⁵⁶Mn) for about the same half-life as
Ray (β^-And γ-rays)
b circulates in the slurry preparation section 2 (this
Valve 10f is closed). Here, the coal slurry is irradiated
Radiation dose is 10^Two~Ten^TenIt is about X-ray.

When the above-mentioned predetermined radiation irradiation is completed, the valve
10f is opened, the coal slurry is guided to a separator 47 using magnetism, and the artificial radioactive isotope fine particles coated with nickel on the surface are recovered from the coal slurry by a magnetic action, and then the slurry is pumped using a plunger type slurry pump or the like. The coal slurry flows through the pressure pump 10c.
At the time of flowing to the pressure pump 10c, the coal slurry is
When the pressure is increased to 00 atm, the hydrogen supplied from the hydrogen storage tank 15 is also increased to the same pressure by a compressor or the like. The pressurized coal slurry is heated by the heater 16 to about 350 to 450 ° C. The reaction temperature in the subsequent liquefaction reactor 17 is about 400 to 500 ° C., and the pressure is the pressure increased by the pressurizing pump 10c.
The residence time in 17 is about 40-80 minutes.

The product obtained by the coal liquefaction reaction in the liquefaction reactor 17 is sent to a reaction product separator 18 where the product gas (including high-pressure gas), water and light and medium oils are contained. (A fraction having a boiling point of less than 260 ° C.) (a first separated component) and heavy oil (a fraction having a boiling point of 260 ° C. or more) and a component (a second separated component) composed of a residue. You. Among them, the first separated component consisting of product gas, water and light medium oil is sent to a first distillation column 19 for normal pressure distillation through a pressure reducing valve (not shown), and the product gas, water and light medium oil It is separated into oil components and separated and stored in the product gas storage tank 20, light and medium oil storage tank 21, and water storage tank 22.

On the other hand, the second separated component consisting of heavy oil and residue (residue) in the reactive organism separation device 18 is sent to a second distillation column 23 for distillation under reduced pressure through a pressure reducing valve (not shown). The distillation column 23 performs distillation under reduced pressure (reduced pressure to 1.3 to 11 kPa), and the fraction having a boiling point of 538 ° C. or higher is discharged and stored as a liquefied residue (residue) in a residue component tank 24. Also,
The heavy oil of the boiling point fraction at 260 to 538 ° C is once returned to normal pressure, then pressurized by a high-pressure circulation pump 10e, and heated to a high temperature by a heater (not shown) to form a Ni-Mo catalyst or It is sent to a fixed-bed hydrogenation reaction tank 25 filled with a substance carrying a Co-Mo catalyst or the like.

Then, the hydrogen introduced from the hydrogen storage tank 15 is also pressurized and 270 to 380 in the hydrogenation reaction tank 25 under a hydrogen atmosphere.
A hydrogenation reaction is carried out at 80 ° C. and 80 to 120 atm for 1 to 2 hours to produce a hydrogenated solvent comprising components such as tetralin. Here, the obtained hydrogenated solvent is returned to the solvent storage tank 12, and is circulated and used as a coal liquefaction solvent.

In the irradiated coal liquefaction plant of the present embodiment, thermal neutrons generated in the reactor 5 are used to
An artificial radioisotope that undergoes beta decay with a half-life of several minutes to several hours is generated, and this artificial radioisotope is mixed with pulverized coal, a catalyst, and a solvent, and irradiated as a pretreatment for the coal liquefaction reaction. By this radiation treatment, β-rays and γ-rays can effectively relax the coal structure, and the efficiency of hydrocracking in the subsequent liquefaction can be improved.
That is, compared to the conventional coal liquefaction method, a desired liquefied oil yield can be achieved under low-temperature and low-pressure conditions, and the construction cost and operation cost of the coal liquefaction apparatus can be reduced.

That is, an artificial radioisotope that undergoes β decay with a half-life of several minutes to several hours is produced around the reactor 5,
A configuration for supplying the radioactive element to the adjacent coal liquefaction system 3 is adopted. Therefore, it functions as a low-cost coal liquefaction plant using thermal neutrons of the nuclear power generation system 1 without directly bringing a large amount of combustible materials into the nuclear power generation system 1.

Further, since the half-life of the radiation is short and the radiation is reduced to the natural radiation level or less in a short time, it is easy to handle the artificial radioactive isotope after the use of irradiation. Processing is close to normal temperature and normal pressure,
The process including the devices required for the pre-processing can be simply configured.

The surface of the fine particles of the artificial radioisotope material is coated with nickel, and is recovered from the coal slurry in the form of fine particles of the artificial radioisotope by using the magnetic action. Can be effectively reused, and the radioactive material is limited to the nuclear power generation system 1 to the slurry preparation unit 2,
Most of the coal liquefaction system 3 can be handled in the same manner as ordinary equipment.

Further, the transfer of the artificial radioisotope fine particles is performed by using a carbon carrier 49 and a gas carrier system (9, 10a, 4).
8), the transfer speed inside the thermal neutron irradiation device 8 and the transfer speed outside can be changed, and the high-speed transfer from the thermal neutron irradiation device 8 to the slurry preparation tank 14 can be performed. Can be made longer.

Next, an irradiation coal liquefaction plant according to a second embodiment of the present invention will be described. In this embodiment, a thermal neutron irradiation device 8 is incorporated in a shroud 5b in a reactor pressure vessel 5a of a nuclear power generation system 1, and natural elements such as silicon (Si), titanium (Ti), and chromium (C
r), isotopes ³⁰ Si, ⁵⁰ Ti, ⁵⁴ Cr, which are concentrated and separated from nickel (Ni), copper (Cu), zinc (Zn), etc.
The microparticles containing ⁶⁴ Ni, ⁶⁵ Cu, ⁶⁸ Zn or the like is included in the transport element made of carbon, via the nozzle holes provided in the body portion of the reactor pressure vessel 5a supplies a stream to the thermal neutron irradiation device 8 This is irradiated with thermal neutrons to generate artificial radioactive elements, and this artificial radioactive element having a short half-life is mixed with fine coal particles, a solvent, a catalyst, and the like, and coal is liquefied at a high temperature and high pressure.

That is, this embodiment has the same configuration as that of the first embodiment (see FIG. 1).
Isolate ³⁰ Si, ⁵⁰ Ti, ⁵⁴ Cr, ⁶⁴ Ni, ⁶⁵ Cu, ⁶⁸ Zn etc. which are isotopes of Si, Ti, Cr, Ni, Cu, Zn, etc., and irradiate them with thermal neutrons. Nuclide conversion to short radioactive elements is used for coal liquefaction.

Here, as a method of separating isotopes, there are an electromagnetic separation method and a laser separation method, which are an isotope separation method whose separation coefficient is ideally infinite. In this embodiment, isotopes are separated by a laser separation method. FIG.
An isotope separation system using selective multistage ionization using a visible light pulse laser or generating microclusters in an excited state from the ground level will be described with reference to FIG.

In this isotope separation system, the visible light pulse laser beam 65 oscillated by driving the visible light pulse laser oscillation device 53 is formed into a slit shape using an optical system, and is separated from the metal element for separation on the rotary cylinder 66. The surface of the artificial radioisotope generation material supply film 62 is irradiated so as to be focused, and the artificial radioisotope generation material is evaporated. The rotating cylinder 66 is driven to rotate, and runs on the artificial radioisotope generation material supply film 62 to be wound around the winding cylinder 67. As a result, a portion irradiated with the laser beam 65 and evaporated is excluded from the laser irradiation position, and a new portion is always moved to the laser irradiation position.

The vaporized artificial radioisotope generating material is conveyed to the supersonic nozzle 55 by helium gas 60. In a region 64 in front of the ejection port of the supersonic nozzle 55, pulsed laser light having three types of resonance absorption wavelengths (usually this type) is used to optically excite and ionize the isotope of interest of the artificial radioisotope generation material in, for example, three stages. The laser light is a wavelength of visible light (the laser light becomes the wavelength of the visible light), and the isotope of interest is ionized by irradiating the synthesized laser light. Since the resonance absorption cross section for performing excitation for ionization in the third stage is smaller than the other stages, the absorption cross section becomes a rule condition when ionization is performed. Therefore, it may be considered to set the first-stage excited state without performing ionization.

In the region 64 in front of the ejection port of the supersonic nozzle 55, the evaporated artificial radioisotope generating material is cooled while causing collision with the helium gas 60 as the carrier gas to form microclusters. In the process of forming microclusters, elements that are ionized or excited from the ground level and those that do not have different microcluster formation probabilities, and microclusters having an isotope ratio different from the natural isotope ratio are formed. Elements that are ionized or excited from the ground level remain as a simple substance, and the supersonic nozzle
It is ejected together with the carrier gas from the 55 ejection ports.

The vapor of the artificial radioisotope-generating material containing microclusters spouted from the spout of the supersonic nozzle 55 undergoes adiabatic expansion and becomes a frozen flow. This frozen flow passes through the electron cloud generated by the electron shower generator 57 and is ionized. When the ionized frozen flow passes between the electrodes of the recovery device 58 to which the electric field has been added, the microcluster, the single atom, and the carrier gas have different masses and different velocities, and are separated by the electric field. Artificial radioactive isotopes produced timber wanted done concentrated excited from the ground state or ionized before the supersonic nozzle jet ⁽³⁰ Si, ⁵⁰ T
^{i, 54 Cr, 64 Ni,} 65 Cu, 68 Zn) speed remains alone is captured collected reach the separation element collection membrane 63 for fast.

When a certain amount of the artificial radioisotope generation material adheres, the separation element recovery membrane 63 is wound up and a new membrane surface is exposed for recovery. Artificial radioisotope generation timber of the separation elements recovered film ^{63 (30 Si, 50 Ti,} 54 Cr, 64 N
When the recovery of (i, ⁶⁵ Cu, ⁶⁸ Zn) is completed, the artificial radioisotope generation material is separated from the film, and fine particles processing of the artificial radioactive element generation material is performed. The helium gas as the carrier gas is discharged as an exhausted helium gas 61, purified, and circulated again as the helium gas 60 for use.

Further, the above-mentioned visible light pulse laser oscillation device
The visible light pulsed laser beam 65 oscillated from 53 irradiates the surface of the artificial radioisotope generation material supply film 62 on the rotating cylinder 66 as described above to evaporate the separation metal element. Only the part is used, and the rest is reflected and enters the visible light pulse laser focusing device 56. The incident visible light pulse laser light is guided to a microalgae culturing system or the like via a laser light transmission pipe or the like (not shown).

The irradiated coal liquefaction plant according to this embodiment basically has the same functions and effects as those of the first embodiment, but also has the following effects.

That is, as for silicon Si, only ³⁰ Si absorbs thermal neutrons and is converted into an nuclide as an artificial radioisotope, and its abundance ratio is 3.09%. Is about 32 times more efficient than natural elements.

In the case of titanium Ti, only ⁵⁰ Ti absorbs thermal neutrons and converts into nuclides as artificial radioisotopes.
Since this is 5.34%, the efficiency of artificial radioisotope generation is approximately 19
Double.

In the case of chromium Cr, ⁵⁰ Cr is converted into a radioisotope having a long half-life when nuclide conversion is performed with thermal neutrons, and it is necessary to remove this. However, the abundance ratio of ⁵⁴ Cr suitable nuclide as artificial radioactive isotopes 2.38%
Therefore, by performing the isotope separation, the efficiency of artificial radioisotope generation is increased by about 42 times as compared with the case of natural elements.

In the case of nickel Ni, ⁵⁸ Ni and ⁶² Ni undergo radionuclide conversion by thermal neutrons, and are converted to radioisotopes having a long half-life. Therefore, it is necessary to remove them. However, ⁶⁴ Ni suitable nuclide as artificial radioactive isotopes
Since the abundance ratio of isotope is 1.08%, the isotope separation increases the efficiency of artificial radioisotope generation by about 93 times compared to the case of natural elements.

In the case of copper Cu, when ⁶³ Cu is converted into a radioisotope having a long half-life by nuclide conversion with thermal neutrons, it must be removed. However, the abundance ratio of ⁶⁵ Cu suitable for nuclide conversion as an artificial radioisotope is 30.9%.
Since it is 1%, the efficiency of artificial radioisotope generation is approximately three times greater than that of natural elements by isotopic separation.

In the case of zinc Zn, when ⁶⁴ Zn is converted into a radioisotope having a long half-life when nuclide conversion is carried out by thermal neutrons, it is necessary to remove this. However, since the abundance ratios of ⁶⁸ Zn and ⁷⁰ Zn, which are suitable for nuclide conversion as artificial radioisotopes, are 18.57% and 0.62%, the efficiency of artificial radioisotope generation is higher than that of natural elements by isotopic separation. About 5 times and about 161 times compared to

Further, if a method of inhibiting microclustering by adopting a state in which the isotope of interest is selectively excited by laser light during the process of generating microclusters is employed, it is possible to perform microclustering by performing ionization by multistage excitation. Isotope separation efficiency because the photoreaction probability is higher than that of the method for inhibiting the isomerization.

Next, a third embodiment of the present invention will be described. The irradiation coal liquefaction plant of this embodiment is:
As shown in FIG. 5, the supply of the artificial radioisotope generation material to the thermal neutron irradiation device 8 incorporated as a part of the shroud 5b in the reactor pressure vessel 5a, and the preparation of the generated (manufactured) artificial radioisotope slurry There is a feature in the configuration of supply to the tank 14.

That is, fine particles of the artificial radioisotope generating material are supplied to the thermal neutron irradiator 8 through the nozzle hole 5g provided at the lower part of the reactor pressure vessel 5a, and the neutrons are irradiated with the thermal neutrons to halve them. An artificial radioactive element having a short period is generated, and the artificial radioactive element is transferred to the slurry preparation tank 14 through another nozzle hole 5g provided in the lower part of the reactor pressure vessel 5a, and then the coal fine particles, the solvent, and the catalyst are removed. This is a radiation irradiation coal liquefaction plant that liquefies coal under high temperature and high pressure conditions by mixing it. Other configurations are the first
This is the same as the embodiment.

The irradiated coal liquefaction plant of this embodiment basically operates in the same manner as the first embodiment, and produces the same effects. Further, since piping to the thermal neutron irradiation device 8 is not made through the trunk nozzle hole 5g of the reactor pressure vessel 5a, workability is not impaired for the disassembly and inspection work of the internal pump 5f. .

Next, a fourth embodiment of the present invention will be described. In this embodiment, as shown in FIG. 6, a thermal neutron irradiator 8 is installed in a reactor pressure vessel 5a between an outer peripheral surface of a shroud 5b and a thermal neutron irradiator 8a.
Supply of artificial radioisotope generating material to
A slurry preparation tank for the generated (manufactured) artificial radioisotope
There is a feature in the composition of supply for 14.

That is, fine particles of the artificial radioisotope generating material are supplied to the neutron irradiation device 8 via the nozzle hole 5g provided in the body of the reactor pressure vessel 5a, and the neutron irradiation device 8 irradiates the neutron irradiation device 8 with heat neutrons to reduce the amount by half. An artificial radioactive element having a short period is generated, and this artificial radioactive element is supplied to the slurry preparation tank through another nozzle hole 5g provided in the same body of the reactor pressure vessel 5a.
This is a radiation-irradiated coal liquefaction plant that liquefies coal after being transferred to 14 and then mixed with fine coal particles, solvents, catalysts, etc., and brought to high temperature and high pressure. Other configurations are the same as those of the first embodiment.

In the present embodiment, as shown in an enlarged view of a main part in FIG. 7, a material for producing an artificial radioisotope is formed through a nozzle hole 5g provided in a lower part of a reactor pressure vessel 5a. The fine particles are supplied to the neutron irradiation device 8 and irradiated with thermal neutrons to generate an artificial radioactive element having a short half-life. The artificial radioactive element is supplied to another nozzle hole provided in the lower part of the reactor pressure vessel 5a. After transferring to the slurry preparation tank 14 via 5 g, the mixture may be mixed with fine coal particles, a solvent, a catalyst and the like, and may be liquefied at a high temperature and a high pressure.

The irradiated coal liquefaction plant of this embodiment and its modification basically operates in the same manner as the first embodiment, and produces the same effects. In addition, since the thermal neutron irradiation device 8 is installed between the reactor pressure vessel 5a and the shroud 5b, it is possible to easily take out the thermal neutron irradiation device 8 outside the vessel when performing maintenance.

Next, a fifth embodiment of the present invention will be described. This embodiment is characterized in that a thermal neutron irradiation device 8 is incorporated and disposed between a reactor pressure vessel 5a and a shield 5c as shown in FIG. That is, fine particles of the artificial radioactive isotope generating material are supplied to the neutron irradiation device 8 through the body of the reactor containment vessel 5d and the body of the shielding body 5c, respectively, and the neutrons are irradiated with thermal neutrons to halve the half life. Is generated, and the artificial radioactive element is transferred to the slurry preparation tank 14 through the same trunk of the reactor containment vessel 5d and the shield 5c, and then transferred to the slurry preparation tank 14. This is a radiation irradiation coal liquefaction plant that liquefies coal under high temperature and high pressure conditions by mixing it. Other configurations are the first
This is the same as the embodiment.

The irradiated coal liquefaction plant of this embodiment basically operates in the same manner as the first embodiment and produces the same effects. Since the thermal neutron irradiation device 8 is installed between the reactor pressure vessel 5a and the shield 5c,
When the maintenance of the thermal neutron irradiation device 8 is performed, the removal operation can be easily performed. Further, the number of nozzle holes attached to the reactor pressure vessel 5a is reduced, so that the manufacture of the reactor pressure vessel 5a is facilitated and the reliability is increased.

Next, a sixth embodiment of the present invention will be described. This embodiment adopts a configuration in which a thermal neutron irradiation device 8 formed in the same shape as the outer shape of the core fuel is incorporated and arranged in a core region in a reactor pressure vessel 5a, as shown in FIG. There are features. That is, fine particles of the artificial radioisotope generating material are supplied to the neutron irradiation device 8 through the nozzle hole 5g provided at the lower part of the pressure vessel 5a, and the artificial radioactive element having a short half-life is irradiated by irradiating the neutron irradiation device 8 with this. Is generated, and this artificial radioactive element is passed through another nozzle hole 5g provided in the lower part of the pressure vessel 5a.
A radiation irradiation coal liquefaction plant that transfers the slurry to a slurry preparation tank 14, mixes it with coal fine particles, a solvent, a catalyst, and the like, and liquefies the coal under a high temperature and high pressure state. Other configurations are the same as those of the first embodiment.

The coal liquefaction plant according to this embodiment basically has the same function and effect as the first embodiment. However, as described above, the thermal neutron irradiation device is installed in the reactor core. 8 and the shroud 5
b. It is possible to irradiate about three times as much thermal neutrons as compared to the case where it is arranged close to b or its outer peripheral surface.
The irradiation time of thermal neutrons can be greatly reduced.

Next, a seventh embodiment of the present invention will be described. This embodiment is a high-temperature gas-cooled nuclear power generation system in which the nuclear power generation system 1 shown in FIG. 1 uses helium gas as a coolant, and as shown in FIG. Area or fixed reflector area,
It is characterized in that a thermal neutron irradiation stand pipe 71 formed in the same shape as that of the movable reflector 69 or the fixed reflector 70 is incorporated and arranged.

That is, as shown in an enlarged view of a main part in FIG. 10, a stand pipe 71 for irradiating thermal neutrons is attached through nozzle holes provided in the upper and lower parts of the pressure vessel 68, and the inside thereof is artificially inserted. A carrier made of carbon containing fine particles of a radioisotope generation material is loaded with a carrier gas. Then, this carrier is irradiated with thermal neutrons to generate an artificial radioactive element having a short half-life, and transferred to the slurry preparation tank 14,
A radiation-irradiated coal liquefaction plant that mixes coal fine particles, solvents, catalysts, etc., and liquefies coal at high temperature and high pressure.

In this embodiment, as described above, the thermal neutron irradiation stand pipe 71 is connected to the reactor pressure vessel.
It is configured to be incorporated in the area of the movable reflector 69 or the area of the fixed reflector 70 in 68, and is transported to the thermal neutron irradiation stand pipe 71 by carbon containing fine particles of an artificial radioisotope generation material. The transfer of the child is performed by mounting the carrier on the carrier mounting device 73 and injecting the carrier gas from the carrier gas storage tank 9 into the carrier mounting device 73 by the carrier gas injection pump 72.

The irradiated coal liquefaction plant of this embodiment basically operates in the same manner as the first embodiment, and produces the same effects. A thermal neutron irradiation stand pipe 71 is incorporated in the movable reflector 69 area or the fixed reflector 70 area of the reactor pressure vessel 68, and a carrier for transporting the artificial radioactive isotope generating material in the stand pipe 71 is controlled. Because of the phase transfer, the structure inside the reactor pressure vessel 68 can be simplified, and unlike the thermal neutron irradiation device 8 in the first to sixth embodiments, the production is easy and the reliability is high. Coal liquefaction plant with high quality can be provided. Inspection and maintenance work is also easy.

Next, an eighth embodiment of the present invention will be described. In this embodiment, the illustration is omitted, but in the irradiation coal liquefaction plant of the first to seventh embodiments, the nuclear power generation system 1 uses the shield 5c or the primary material outside the reactor pressure vessel 5a or 68. A configuration is adopted in which the coal slurry distribution / circulation pipe from the coal slurry preparation tank 14 is incorporated between the biological shield walls, and the incorporation of the thermal neutron irradiation device 8 or the thermal neutron irradiation stand pipe 71 is eliminated. Then, coal fine particles, a solvent, a catalyst, and the like are put and mixed in the coal slurry preparation tank 14 and partially flowed to the circulation pipe between the shield 5c or the primary biological shield wall 79 outside the reactor pressure vessel 5a or 68. Guiding coal slurry γ
This is a radiation irradiation coal liquefaction plant that irradiates coal to liquefy coal under high temperature and high pressure.

The coal liquefaction plant of this embodiment basically operates in the same manner as the coal liquefaction plants of the first to seventh embodiments, and produces the same effects, but the coal slurry is directly atomized. In order to prepare a coal slurry by irradiating it to the outside of the furnace pressure vessel and irradiating it with gamma rays, it is also simultaneously irradiated with thermal neutrons and converts the elements contained in the coal slurry into nuclides, producing long-lived artificial radioactive elements Therefore, the irradiation time is set to be shorter than the time during which the radiation dose remains below the natural radiation dose even if nuclide conversion occurs. In addition, it is necessary to take measures to prevent the spread of accidents even if a fire accident occurs because combustible materials are put inside the containment vessel. However, equipment for producing an artificial radioisotope and radiation irradiation equipment using the same are not required, and the system configuration is simplified.

Next, a ninth embodiment of the present invention will be described. FIG. 11 is a block diagram illustrating a schematic configuration of the irradiated coal liquefaction plant of this embodiment. This coal liquefaction plant is a hydrogen storage tank according to the first embodiment.
Instead of 15, a water electrolysis device 30, a water supply path 31 for supplying pure water to the water electrolysis device 30, and an oxygen storage tank 32 for storing oxygen generated by electrolysis in the water electrolysis device 30 are provided. . That is, pure water is supplied to the water electrolysis device 30, and the pure water is electrolyzed by the electric power generated by the nuclear power generation system 1,
While oxygen is stored in the oxygen storage tank 32, hydrogen is supplied to the liquefaction reactor 17 of the coal liquefaction system 3. The water electrolysis device 30 generally uses an alkaline aqueous solution electrolyte (conversion efficiency 60 to 80%), but may use a solid polymer membrane.

This embodiment has basically the same operation and effect as the first embodiment, but has the following operation and effect. That is, nighttime power demand is about 60% of the daytime peak demand, so surplus power (about 40% of nighttime power) is used to generate hydrogen and oxygen, of which hydrogen is converted to coal. The coal is supplied to the liquefaction system 3 to liquefy the coal. Therefore, the operation efficiency of the nuclear power generation system 1 is improved. As described above, by using the nighttime electric power of the nuclear power generation system 1 to produce hydrogen in the water electrolysis device 30 and supply it to the coal liquefaction system 3, the load leveling of the nuclear power generation system 1 can be obtained. In addition, since hydrogen obtained by electrolysis is not stored and used immediately for coal liquefaction, equipment for storing a large amount of hydrogen is not required.

Next, a tenth embodiment of the present invention will be described. This embodiment is based on the configuration of the ninth embodiment as shown in FIG.
This is an irradiation coal liquefaction plant that is configured to include a refrigerant production system 86, a cryogenic carbon dioxide / oxygen liquefaction system 34, a storage cold energy conversion system 35, a generated gas power generation system 36, and the like.

That is, the radiation-irradiated coal liquefaction plant of this embodiment includes a mixed medium system 85 and a refrigerant production system 86 using the exhaust steam (or extracted steam) of the power generation steam turbine 6 of the nuclear power generation system 1. A cryogenic carbon dioxide / oxygen liquefaction system 34 for removing the heat generated by the compressor using the cold heat of the refrigerant production system 86 is connected to the generated gas power generation system 36.

FIG. 13 shows details of the mixed medium system 85 and the refrigerant production system 86. That is, the medium-concentration mixed medium pressurized by the pressurizing pump 93 is heated by exchanging heat with the low-concentration mixed-medium liquid of the medium-pressure separator 89 in the heat exchanger 99, and further restored by the nuclear power generation system 1. Heated by the exhaust gas (or bleed air) of the steam turbine 6 in the water device 7, guided to the high-pressure separator 88 and separated into a high-concentration mixed medium vapor and a low-concentrated mixed medium liquid. Then, the mixture is guided to the mixed medium turbine 87 and driven to generate electric power by the coaxially coupled generator 94.

The remaining high-concentration mixed-medium vapor branched before the mixed-medium turbine 87 is led to a condenser 92 where a medium-concentration mixed-medium liquid pressurized by a pressure pump 93 is diverted. It exchanges heat with the deep seawater 95 and is cooled and recondensed, adiabatically expanded by the expansion valve 96 of the refrigerant production system 86 to become a refrigerant, and heat exchanged by the cryogenic carbon dioxide / oxygen liquefaction system 34. Then, the flow returns to the absorber 97 of the refrigerant production system 86.

The low-concentration mixed medium liquid generated in the high-pressure separator 88 is guided to the medium-pressure separator 89 via the pressure reducing valve 98 and is separated into a high-concentration mixed medium vapor and a low-concentrated mixed medium liquid. . Then, the high-concentration mixed-medium vapor is guided to the middle stage of the mixed-medium turbine 87, which is driven to generate power.

The low-concentration mixed medium liquid separated by the medium-pressure separator 89 exchanges heat with the medium-concentration mixed medium liquid pressurized by the pressurizing pump 93 in the heat exchanger 99 to be cooled and branched. Through the throttle valve 100 to the absorber 90, mixed and absorbed with the exhaust gas of the mixing medium turbine 87, guided to the condenser 91, and cooled by exchanging heat with seawater (deep cold seawater) 95. And return to liquid.

The remaining low-concentration mixed medium liquid separated and branched by the intermediate pressure separator 89 is guided to the absorber 97 of the refrigerant production system 86 via the throttle valve 101, where the cryogenic carbon dioxide gas
The high-concentration mixed medium that has exchanged heat in the oxygen liquefaction system 34 is absorbed and guided to the condenser 102, where it exchanges heat with seawater (deep cold seawater) 95 to return liquid. This mixed medium liquid joins with the mixed medium liquid condensed in the liquid condensing device 91 of the mixed medium system 85 and is led to the inlet side of the pressure pump 93.

The mixed medium liquid pressurized by the pressurizing pump 93 is branched and heated by exchanging heat with the condenser 92, and the remaining part is mixed with the low-concentration mixed medium liquid separated by the medium-pressure separator 89. Heated by heat exchange in the heat exchanger 99, these heated mixed medium liquids are merged and separated again, and a part is guided to the intermediate pressure separator 89 via the pressure reducing valve 103, and the remaining Is guided to the condenser 7 of the nuclear power generation system 1 and heated.

In summary, the high-concentration mixed medium condensed in the condenser 92 of the mixed medium system 85 undergoes adiabatic expansion by the expansion valve 96 of the refrigerant production system 86 to become a refrigerant, and becomes a cryogenic carbon dioxide gas. -Heat is exchanged by the oxygen liquefaction system 34, heated and returned, guided to the absorber 97, exchanged with seawater (deeply cold seawater) 95, cooled, and returned, and the returned liquid is mixed with the mixed medium system. The configuration is such that it is guided to the inlet side of the 85 pressure pump 93. The mixed medium is composed of an aqueous ammonia solution and an aqueous ethanol solution.

FIG. 14 shows the details of the cryogenic carbon dioxide / oxygen liquefaction system 34 shown in FIG. That is, the expansion valve 96 and the absorber 97 of the refrigerant production system 86 and the heat exchange system 112, 113, 114, 115 are connected by a heat circuit, and the expansion turbines 118, 119 and the liquid carbon dioxide gas storage tank are connected.
38, the liquid oxygen storage tank 37 is connected by a heat circuit via a heat exchange system 116, and the pump 129 of the storage cooling and heat conversion system 35 and the heat exchangers 110 and 111, the heat exchange systems 112 to 11
And 5 are connected by a thermal circuit.

In such a circuit, the compressor 10
The nitrogen gas is pressurized in 4, and in the heat exchange system 112, cooled by the mixed medium refrigerant generated in the refrigerant production system 86 and the refrigerant stored in the storage cooling / heat conversion system 35, and purified.
Impurities are removed at 107 and adiabatically expanded to liquid nitrogen by an expansion turbine 117, heat exchanged by a heat exchange system 116 to become nitrogen gas, cooled by the heat exchange system 114 and circulated to the compressor 104.

Further, the carbon dioxide gas generated by the generated gas power generation system 36 is cooled by the heat exchanger 111 with the refrigerant stored in the storage cooling / heat conversion system 35, guided to the compressor 105 and pressurized, and further cooled by the heat exchanger 110. It is cooled by the refrigerant from the storage cold energy conversion system 35, impurities are removed by the purification device 108, adiabatic expansion is performed by the expansion turbine 118 to form liquid carbon dioxide, and heat exchange is performed by the heat exchange system 116 to perform liquid carbon dioxide storage. Three
Store in 8.

The oxygen generated in the water electrolyzer 30 is cooled by the heat exchange system 115 with the refrigerant from the refrigerant production system 86 and the refrigerant from the storage cooling and heat conversion system 35, and then guided to the compressor 106 to be pressurized. In the exchange system 113, the refrigerant is cooled by the refrigerant from the refrigerant production system 86 and the refrigerant from the storage cooling and heat conversion system 35, impurities are removed by the purifier 109, and adiabatic expansion is performed by the expansion turbine 119 to form liquid oxygen, and the heat exchange system 116 FIG. 15 in which heat is exchanged and stored in the liquid oxygen storage tank 37 is the generated gas power generation system 36 in FIG.
3 shows details of a storage cold heat exchange system 35. FIG. That is, the generated gas power generation system 36 includes a combustor 120, a gas turbine 121, a waste heat recovery boiler 122,
3, composed of a condenser 124, a heat exchanger 125 and the like. Condenser 124
And pressurizing pump 9 for heat exchanger 125 and mixed media system 85
3 and the high pressure separator 88 are connected by a thermal circuit. Further, the generated gas is supplied to the combustor 120 from the generated gas storage tank 20. Further, the heat exchanger 125 and the heat exchanger 111 of the refrigerated carbon dioxide / oxygen liquefaction system 34 are connected by a heat circuit, and waste gas composed of water vapor and carbon dioxide is transferred.

The storage cooling / heating conversion system 35 includes the pressure pump 12
6, 127, a heat exchanger 128, pumps 129 and 130, a low-temperature refrigerant storage tank 131, a high-temperature refrigerant storage tank 132, and the like. Then, the liquid carbon dioxide gas storage tank 38, the pressurizing pump 127, and the liquid oxygen storage tank 3
7 and the pressurizing pump 126 are connected by a heat pipe. Also,
The liquid carbon dioxide pipe and the liquid oxygen pipe via the heat exchanger 128 are connected to the combustor 120 of the product gas power generation system.

Liquid oxygen storage tank 37, liquid carbon dioxide gas storage tank 38
The liquid oxygen and liquid carbon dioxide gas are pressurized by the pressurizing pumps 126 and 127, exchange heat with the liquid propane refrigerant in the heat exchanger 128, become high-pressure gas, and are guided to the combustor 120. The liquid propane refrigerant is transferred from the pump 129 to the heat exchange system of the refrigerated carbon dioxide / oxygen liquefaction system 34 and exchanges heat.
This is a configuration that returns to the high-temperature refrigerant storage tank 132.

Next, the operation of the irradiated coal liquefaction plant of this embodiment will be described. That is, during the daytime when power demand is high, the combustor 120 of the generated gas power generation system 36
Guide the product gas stored in the product gas storage tank 20, and
In the storage cooling / heating conversion system 35, the liquid oxygen and the liquid carbon dioxide stored in the liquid oxygen storage tank 37 and the liquid carbon dioxide storage tank 38 are heated and vaporized, respectively, and then guided to the combustor 120 for combustion. The waste gas of this combustor 120 is
The gas turbine 121 is driven to rotate a generator to generate power.

The exhaust gas of the gas turbine 121 generates steam in the waste heat recovery boiler 122 and then drives the steam turbine 123 for power generation with the steam. The exhaust of the steam turbine 123 is supplied to the pressurizing pump 93 of the mixed medium system 85 by the condenser 124.
The condensed medium is condensed with heat by exchanging heat with the mixed medium having a higher concentration, and is guided to the waste heat recovery boiler 122 to exchange heat with the exhaust gas of the gas turbine 121 to become steam.

The waste gas that has undergone heat exchange in the waste heat recovery boiler 122 is subjected to heat exchange in the heat exchanger 125 and then guided to the heat exchanger 111 of the cryogenic carbon dioxide / oxygen liquefaction system 34 where it is dehumidified. The remaining carbon dioxide gas is liquefied via the compressor 105, the heat exchanger 110, the refining device 108, the expansion turbine 118, and the heat exchange system 116 and stored in the liquid carbon dioxide gas storage tank 38.

The heat exchanger 125 heats the medium by exchanging heat with the medium-concentration mixed medium transferred from the pressurizing pump 93 of the mixed medium system 85. The medium-concentration mixed medium heated by the heat exchanger 125 and the condenser 124 is transferred to the high-pressure separator 88 of the mixed-medium system 85, and is separated into a high-concentration mixed-medium vapor and a low-concentration mixed-medium liquid. The mixed-medium steam drives the mixed-medium turbine 87 to generate power.

When nighttime power demand is low, pure water is electrolyzed in the water electrolyzer 30 to produce oxygen and hydrogen, of which oxygen is sent to the heat exchange system of the cryogenic carbon dioxide / oxygen liquefier system 34. The liquid is sequentially liquefied via a compressor 106, a heat exchange system 113, a refining device 109, an expansion turbine 119, and a heat exchange system 116, and stored in the liquid oxygen storage tank 37. On the other hand, hydrogen is supplied to the coal liquefaction reactor 17 of the coal liquefaction system 3 to liquefy coal.

The radiation-irradiated coal liquefaction plant of this embodiment basically has the same functions and effects as those of the ninth embodiment, but also has the following functions and effects. That is, it is possible to cope with daytime peak power demand using oxygen obtained by electrolysis of water and coal-producing gas produced by thermal power and night-time neutrons, contributing to load leveling of nuclear power generation systems. it can. In addition, carbon dioxide gas is used as an inert gas to be mixed and diluted at the time when the coal-produced gas is oxy-combusted, so that the combustion gas is composed of carbon dioxide gas and water vapor. Removal can be easily performed.

Further, by providing a mixed medium system and a refrigerant production system as a bottoming cycle of a nuclear power generation system, heat energy generated in a nuclear reactor can be recovered to a low temperature, thereby improving thermal efficiency and reducing exhaust heat. Can be achieved. Refrigerant is manufactured using nuclear energy at night, and this refrigerant is used for liquefaction of oxygen at night and can be used for liquefaction and recovery of carbon dioxide during the day. Can be.

Next, an eleventh embodiment of the present invention will be described. In this embodiment, as shown in FIGS.
Based on the configuration of the tenth embodiment, instead of the product gas power generation system 36, a residue gasification power generation system 44 having a substantially similar configuration is provided, and a residue gasification furnace 43 is attached to the residue gasification furnace 43 to replace the residue gas instead of the product gas. Is supplied to the residue gasification power generation system 44.

That is, the radiation-irradiated coal liquefaction plant according to the present embodiment includes a mixed medium system 85, a refrigerant production system 86, and a refrigerant production system 86 that use the exhaust or extracted steam of the power generation steam turbine 6 of the nuclear power generation system 1. The cryogenic carbon dioxide / oxygen liquefaction mechanism 34 that removes the heat generated by the compressor using the cold heat of 86, the residue gasification furnace 43, and the like are connected to the residue gasification power generation system 44.

The oxygen produced by the electrolysis in the water electrolyzer 30 is sent to a cryogenic carbon dioxide / oxygen liquefaction system 34 where it is liquefied and stored in a liquid oxygen storage tank 37.
On the other hand, the residue from the residue storage tank 45 and the liquid oxygen storage tank
The liquid oxygen from the 37 and the liquid carbon dioxide from the liquid carbon dioxide storage tank 38 are heated and vaporized by the storage / cooling heat conversion system 35 and supplied to the residue gasification furnace 43, respectively. Then, a residue gas is generated in the residue gasification furnace 43, and the residue gas is guided to the combustor 120 of the residue gasification power generation system 44, and the liquid oxygen and liquid carbon dioxide gas vaporized in the storage cooling / heating conversion system 35 are generated. Is led to the combustor 120 by another route to perform combustion.

The combustion gas from the combustor 120 drives the gas turbine 121 for power generation, and the waste heat is recovered by the waste heat recovery boiler 122 to generate steam and drive the steam turbine 123 for power generation. The waste gas that has undergone heat exchange in the waste heat recovery boiler 122 is led to the heat exchanger 125, and performs heat exchange with the medium-concentration mixed medium pressurized by the pressurizing pump 93 of the mixed medium system 85. The components of the waste gas guided from the heat exchanger 125 to the refrigerated carbon dioxide / oxygen liquefaction system 34 are water vapor and carbon dioxide, and the heat exchangers 111, 110 and the compressor 105 of the refrigerated carbon dioxide / oxygen liquefaction system 34. The liquid carbon dioxide is sequentially passed through the purification device 108, the expansion turbine 118, and the heat exchange system 116, and is stored in the liquid carbon dioxide storage tank 38.

The operation and effects of the irradiation coal liquefaction plant of this embodiment are as follows. That is,
During the daytime when power demand is high, the residue gasification furnace 43 stores the residue in the residue storage tank 45, the liquid oxygen in the liquid oxygen storage tank 37, and the liquid carbon dioxide gas in the liquid carbon dioxide gas storage tank 38 in a cooling and heating conversion system.
The heated (pressurized) and vaporized material is supplied at 35 to generate a residue gas. Here, the generated residue gas is led to the combustor 120 of the residue gasification power generation system 44, and on the other hand, the liquid oxygen from the liquid oxygen storage tank 37 and the liquid carbon dioxide gas from the liquid carbon dioxide gas storage tank 38 are stored and cooled. At 35, the gas is heated and vaporized, guided to the combustor 120, burned, and the combustion gas drives the gas turbine 121 to generate power.

Further, the waste heat of the gas turbine 121 is recovered by the waste heat recovery boiler 122, and the recovered waste heat generates steam to drive the steam turbine 123 to generate power. The waste gas from the waste heat recovery boiler 122 is led to the heat exchanger 125 and exchanges heat with the medium concentration mixed medium pressurized by the pressurizing pump 93 of the mixed medium system 85. The waste gas generated by performing heat exchange in the heat exchanger 125 is composed of water vapor and carbon dioxide gas, and this waste gas is led to the heat exchanger 111 of the cryogenic carbon dioxide / oxygen liquefaction system 34, and is supplied to the compressor 105 The liquid carbon dioxide gas is sequentially passed through the heat exchanger 110, the purification device 108, the expansion turbine 118, and the heat exchange system 116, and is stored in the liquid carbon dioxide gas storage tank 38.

When nighttime power demand is low, pure water is electrolyzed in the water electrolyzer 30 to produce oxygen and hydrogen, of which oxygen is the heat exchange system 115 of the cryogenic carbon dioxide / oxygen liquefaction system 34. The liquid oxygen is sequentially passed through the compressor 106, the heat exchange system 113, the purification device 109, the expansion turbine 119, and the heat exchange system 116, and is stored in the liquid oxygen storage tank 37. On the other hand, hydrogen is coal liquefaction system 3
Where it is used for coal liquefaction.

As described above, the radiation-irradiated coal liquefaction plant according to the present embodiment uses the residue generated and stored when coal liquefaction is performed by night power and thermal neutrons, obtained by electrolysis of water and stored. Gasification is performed using the oxygen that has been generated, and residue gasification power generation is performed in response to peak power demand in the daytime, so that the load on the nuclear power generation system 1 can be leveled. Also, in the oxygen combustion of the residue purified gas,
By using carbon dioxide as the inert gas, the waste gas of the combustion gas is composed of carbon dioxide and water vapor, and the carbon dioxide can be easily removed from the waste gas by liquefaction.

[0122]

According to the radiation liquefaction coal liquefaction plant of the present invention, it is possible to liquefy coal efficiently with high safety by using excess thermal neutrons generated in a nuclear reactor as an energy source. Load leveling can be achieved.

[Brief description of the drawings]

FIG. 1 is a block diagram showing an entire configuration of a radiation-irradiated coal liquefaction plant according to a first embodiment of the present invention.

FIG. 2 is a cross-sectional view showing a reactor part in the irradiation coal liquefaction plant according to the first embodiment of the present invention.

FIG. 3 is a piping diagram for loading / unloading a carrier to / from a thermal neutron irradiation apparatus in the irradiation coal liquefaction plant according to the first embodiment of the present invention.

FIG. 4 is a cross-sectional view of an isotope separation system using a laser-assisted selective excitation and a microcluster generation process in a irradiated coal liquefaction plant according to a second embodiment of the present invention.

FIG. 5 is a cross-sectional view illustrating a nuclear reactor in a radiation-treated coal liquefaction plant according to a third embodiment of the present invention.

FIG. 6 is a cross-sectional view illustrating a reactor part in a radiation-irradiated coal liquefaction plant according to a fourth embodiment of the present invention.

FIG. 7 is a cross-sectional view showing another example of a nuclear reactor section in the irradiated coal liquefaction plant according to the fourth embodiment of the present invention.

FIG. 8 is a cross-sectional view showing a reactor part in a radiation-treated coal liquefaction plant according to a fifth embodiment of the present invention.

FIG. 9 is a cross-sectional view showing a reactor part in a radiation-irradiated coal liquefaction plant according to a sixth embodiment of the present invention.

FIG. 10 is a diagram showing a reactor system and a piping system for handling carriers in an irradiation coal liquefaction plant according to a seventh embodiment of the present invention.

FIG. 11 is a block diagram showing the overall configuration of a radiation-irradiated coal liquefaction plant according to a ninth embodiment of the present invention.

FIG. 12 is a block diagram showing an overall configuration of a radiation-irradiated coal liquefaction plant according to a tenth embodiment of the present invention.

FIG. 13 is a block diagram showing a mixed medium system and a refrigerant production system in an irradiation coal liquefaction plant according to a tenth embodiment of the present invention.

FIG. 14 is a block diagram showing a refrigerated carbon dioxide / oxygen liquefaction system in the irradiation coal liquefaction plant according to the tenth embodiment of the present invention.

FIG. 15 is a block diagram showing a generated gas power generation system and a storage cold energy conversion system in a radiation-irradiated coal liquefaction plant according to a tenth embodiment of the present invention.

FIG. 16 is a block diagram showing an entire configuration of a radiation irradiation coal liquefaction plant according to an eleventh embodiment of the present invention.

FIG. 17 is a block diagram showing a residue gasification power generation system and a storage cold energy conversion system in an irradiation coal liquefaction plant according to an eleventh embodiment of the present invention.

[Explanation of symbols]

REFERENCE SIGNS LIST 1 Nuclear power generation system 2 Slurry preparation unit 3 Coal liquefaction system 4 Product storage unit 5 Reactor 5 a
... pressure vessel, 5b ... shroud, 5c ... shield, 5d ...
Reactor containment vessel, 5e isolation valve, 5f internal pump, 5g nozzle hole, 5h valve, 5i switching valve, 5
j, 5k: radiation detector, 6: steam turbine, 7: condenser, 8: thermal neutron irradiation device, 9: carrier gas storage tank, 10
a compressor, 10b circulation pump, 10c pressure pump, 10d, 10e circulation pump, 10f valve, 11 coal storage tank, 12 solvent storage tank, 13 catalyst storage tank, 14 slurry preparation tank , 15: hydrogen storage tank, 16: heater, 17: liquefaction reactor, 18: reaction product separator, 19: first distillation tower, 20: product gas storage tank, 21: light and medium oil storage tank, 22: water storage tank, 23: second distillation column, 24: residue component tank, 25: hydrogenation reaction tank, 30: water electrolyzer, 31: water supply path, 32: oxygen storage tank, 33: freezing and crushing apparatus , 34 ... refrigerated carbon dioxide / oxygen liquefaction system, 35 ... storage cold energy conversion system, 36 ... product gas power generation system, 37 ... liquid oxygen storage tank, 38 ... liquid carbon dioxide storage tank, 43 ... residue gasification furnace, 44 ... residue gasification power generation system, 45 ... residue storage tank, 47 ... magnetic separator, 48 ... carrier supply device, 49 ... carrier, 50,51,52 ... valve, 53 ... visible light Rusureza oscillator, 55 ... supersonic nozzle, 56 ... visible light pulse laser focusing device, 57 ... electron shower generator, 58 ... recovery device, 60 ... helium gas, 61 ... exhaust helium gas, 62 ...
Artificial radioisotope generation material supply membrane, 63: Separation element recovery membrane, 64: Area in front of jet port, 65: Visible light pulse laser beam, 66
... Rotating cylinder, 67 ... Rewind cylinder, 68 ... Reactor pressure vessel, 69 ... Movable reflector, 70 ... Fixed reflector, 71 ... Stand pipe for thermal neutron irradiation, 72 ... Transport gas injection pump, 73 ... Transporter mounted Equipment, 74, 75: Gate valve, 76: Radiation detector, 77: Reactor containment vessel, 78: Upper shield, 79: Primary biological shield wall, 80
… Diamond grid, 81, 83… valve, 82… radiation detector, 84
... Switching valve, 85 ... Mixed medium system, 86 ... Refrigerant production system, 87 ... Mixed medium turbine, 88 ... High pressure separator, 89 ... Medium pressure separator, 90 ... Absorber, 91 ... Condenser, 92 ... Condenser , 93 ...
Pressurized pump, 94 ... generator, 95 ... seawater (deep cold seawater), 96
... expansion valve, 97 ... absorber, 98 ... pressure reducing valve, 99 ... heat exchanger, 10
0,101 ... Throttle valve, 102 ... Condenser, 103 ... Reducing valve, 104,10
5, 106 ... compressor, 107, 108, 109 ... refining equipment, 11
0, 111 ... heat exchanger, 112, 113, 114, 115, 116 ... heat exchange system, 117, 118, 119 ... expansion turbine, 120 ... combustor, 121 ... gas turbine, 122 ... waste heat recovery boiler, 123 ...
Steam turbine, 124 ... condenser, 125 ... heat exchanger, 126, 1
27 ... Pressure pump, 128… Heat exchanger, 129,130… Pump, 1
31: low-temperature refrigerant storage tank, 132: high-temperature refrigerant storage tank.

──────────────────────────────────────────────────の Continued on the front page (51) Int.Cl. ⁷ Identification code FI Theme coat ゛ (Reference) G21G 1/02 G21G 1/02 G21H 5/00 G21H 5/00 Z (72) Inventor Yutaka Takeuchi Kawasaki, Kanagawa Prefecture 2-1 Ukishima-cho, Ichikawasaki-ku, Japan Toshiba Hamakawasaki Plant (72) Inventor Shigeaki Kadoyama 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture Toshiba Yokohama Office (72) Inventor Hideaki Hioki Yokohama, Kanagawa No. 8 Shinsugita-cho, Isogo-ku, Toshiba, Japan Toshiba Yokohama Office (72) Inventor Tatsuo Miyazawa 1-1-1, Shibaura, Minato-ku, Tokyo Inside Toshiba Head Office

Claims (9)

[Claims] An artificial radioisotope is generated from a material for radioisotope generation by irradiating thermal neutrons disposed in a pressure vessel or a shield of a nuclear reactor generating steam for driving a power generation turbine or a high-temperature high-pressure gas or inside a shield. A nuclear power generation system having a thermal neutron irradiation device to be generated, a coal slurry preparation unit for preparing the coal slurry by mixing the generated artificial radioisotope with coal powder, a solvent and a catalyst, and prepared by the coal slurry preparation unit A coal liquefaction system, comprising: a coal liquefaction system for heating and liquefying and decomposing the separated coal slurry to separate decomposition products. 2. As a material for generating a radioisotope, Al,
The irradiated coal liquefaction plant according to claim 1, wherein at least one of Si, Ti, V and Mn is used. 3. The material for radioisotope generation is separated by isotope.
Was³⁰Si,⁵⁰Ti, ⁵⁴Cr,⁶⁴Ni,⁶⁵Cu and⁶⁸Z
2. The method according to claim 1, wherein at least one of n.
Irradiated coal liquefaction plant. 4. The irradiation time of thermal neutrons on the material for radioisotope generation is about the half-life of the artificial radioactive element to be produced, and after the thermal neutron irradiation, the coal slurry is within 1/10 of the half-life. The irradiated coal liquefaction plant according to claim 1, which is used for preparation. 5. A coal slurry preparation unit in which fine particles of a radioisotope generating material are filled in a carbon carrier and guided to a thermal neutron irradiation device, and the carrier coming out of the thermal neutron irradiation device is transported at high speed by gas. The irradiated coal liquefaction plant according to claim 1, characterized in that the irradiation is performed. 6. A crushing device provided at an entrance side of a coal slurry preparation section for crushing a carrier, and a separation device for guiding only fine particles of a radioisotope generation material to a coal slurry preparation tank are provided. The irradiated coal liquefaction plant according to claim 5, wherein 7. The radiation-irradiated coal liquefaction plant according to claim 5, wherein a ferromagnetic film is formed on the surfaces of the fine particles of the radioisotope generation material filled in the carrier made of carbon. 8. A mixed medium system for cooling exhaust gas or bleed air of a steam turbine of a nuclear power generation system, a refrigerant manufacturing system for manufacturing a refrigerant from a medium separated by the mixed medium system, and removing heat generated by a compressor by the refrigerant. Refrigerated carbon dioxide / oxygen liquefaction system that produces liquid carbon dioxide and liquid oxygen by gasification, and a generated gas power generation system that uses coal gas decomposition gas as fuel or residue gasification that uses coal slurry residue decomposition gas as fuel The irradiated coal liquefaction plant according to claim 1, further comprising at least one of a power generation system. 9. A coal slurry preparation tank for preparing a coal slurry by mixing coal powder, a solvent and a catalyst, a pressure vessel of a nuclear reactor for generating steam or a high-temperature and high-pressure gas for driving a power generation turbine, and a shield or a primary vessel. A radiation pipe for irradiating the coal liquefaction plant, the circulation pipe being provided between living body shield walls and partially irradiating the coal slurry in the coal slurry preparation tank with radiation.