Nuclear reactor shielding equipment, nuclear power equipment, and reactor shielding equipment construction method

Abstract

To provide nuclear reactor shielding facilities which are easier to construct while maintaining high radiation shielding performance.SOLUTION: A nuclear reactor shielding facility for shielding the surroundings of a nuclear reactor installed on an installation surface is provided, the facility comprising a base structure provided along an outer circumference of an area other than the installation surface to surround the entire surroundings of the nuclear reactor other than the installation surface, and a shielding structure provided on an entire surface of the base structure and provided with water filled therein.SELECTED DRAWING: Figure 2

Description

[Technical Field]

[0001] FIELD OF THE DISCLOSURE The present disclosure relates to nuclear reactor shielding systems and methods for constructing shielding systems. [Background technology]

[0002] Nuclear power facilities that use nuclear fuel and utilize the heat of nuclear reactions store the nuclear fuel that undergoes nuclear reactions in a nuclear reactor. There are nuclear power generation systems that generate electricity by utilizing the heat of nuclear reactions. In nuclear power generation systems, the heat generated in the reactor is recovered by a primary cooling system in which primary coolant circulates between the reactor and a secondary cooling system, heat exchange occurs between the primary coolant and the secondary coolant, and power is generated by rotating a turbine installed in the secondary cooling system using the energy of the secondary coolant. The reactor of a nuclear power generation system is stored in a reactor containment vessel, which is further surrounded by a reactor building made of concrete or the like. An example of a building that stores fuel containers that contain spent nuclear fuel is the building described in Patent Document 1. The building described in Patent Document 1 has structures with water-filled walls. [Prior art documents] [Patent documents]

[0003] [Patent Document 1] Patent No. 3601046 Summary of the Invention [Problem to be solved by the invention]

[0004] In recent years, facilities using relatively small nuclear reactors have been considered for use in nuclear power generation facilities, etc. When using such small nuclear reactors, shielding them with highly shielding metals or thick concrete structures makes construction of the entire facility time-consuming.

[0005] The present disclosure is intended to solve the above-mentioned problems, and aims to provide a reactor shielding system, a nuclear power facility, and a method for constructing a reactor shielding system that are easy to construct while maintaining high radiation shielding properties. [Means for solving the problem]

[0006] In order to achieve the above-mentioned object, a reactor shielding system according to one embodiment of the present disclosure is a reactor shielding system that shields the periphery of a reactor installed on an installation surface, and includes a foundation structure that is arranged on the outer periphery other than the installation surface and surrounds the entire periphery of the reactor other than the installation surface, and a shielding structure that is arranged on the entire surface of the foundation structure and is filled with water.

[0007] In order to achieve the above-mentioned object, a nuclear facility according to one aspect of the present disclosure includes a nuclear reactor and the above-described reactor shielding system.

[0008] In order to achieve the above-mentioned objectives, a method for constructing a reactor shielding system according to one aspect of the present disclosure includes the steps of installing a foundation around a reactor installed on an installation surface, placing a container over the entire surface of the foundation, and filling the container with water. [Effects of the Invention]

[0009] According to the disclosure, it is possible to obtain the effect of being easy to construct while maintaining high radiation shielding properties. [Brief explanation of the drawings]

[0010] [Figure 1] FIG. 1 is a schematic diagram showing the general configuration of a nuclear facility according to this embodiment. [Figure 2] FIG. 2 is a schematic diagram showing the general configuration of the nuclear power generation system according to this embodiment. [Figure 3] FIG. 3 is a schematic diagram showing an example of a method for manufacturing a reactor shielding system according to this embodiment. [Figure 4] FIG. 4 is a schematic diagram showing another example of a reactor shielding system. [Figure 5] FIG. 5 is a schematic diagram showing a schematic configuration of a nuclear facility according to another embodiment. DETAILED DESCRIPTION OF THE INVENTION

[0011] Hereinafter, embodiments of the present disclosure will be described in detail with reference to the accompanying drawings. Note that the present invention is not limited to these embodiments. Furthermore, the components in the following embodiments include those that are easily replaceable by those skilled in the art, or those that are substantially identical.

[0012] FIG. 1 is a schematic diagram showing the overall configuration of a nuclear power generation facility according to this embodiment. The nuclear power generation facility shown in FIG. 1 will be described as a nuclear power generation facility that generates electricity using heat generated in a nuclear reactor, but the present disclosure is not limited thereto. The nuclear power generation facility can also be applied to facilities that use heat generated in a nuclear reactor for purposes other than power generation. It can also be used as a facility that produces radioactive materials using radiation generated in a nuclear reactor. The nuclear power generation facility 1 shown in FIG. 1 includes a nuclear power generation system 10 and a reactor shielding facility 11. The nuclear power generation system 10 is installed on an installation surface 6. In this embodiment, the installation surface 6 is the surface that contacts the foundation of the nuclear reactor, which is the surface of the ground 8. The reactor shielding facility 11 is disposed around the nuclear power generation system 10. The nuclear power generation system 10 is completely surrounded by the ground 8 and the reactor shielding facility 11. In other words, the nuclear power generation system 10 is housed in a space surrounded by the ground 8 and the reactor shielding facility 11.

[0013] Fig. 2 is a schematic diagram showing the overall configuration of a nuclear power generation system according to this embodiment. As shown in Fig. 2, the nuclear power generation system 10 includes a reactor unit 12 and a power generation unit 13. The power generation unit 13 includes a heat exchanger 14, a refrigerant circulation means 16, a turbine 18, a generator 20, a cooler 22, a compressor 24, and a reheat exchanger 26.

[0014] The reactor unit 12 includes a reactor 30 and a heat conduction section 32. The reactor 30 includes a reactor vessel 40, a fuel core 42, and a control unit 44. The reactor vessel 40 stores the fuel core 42 therein. The reactor vessel 40 stores the fuel core 42 in a sealed state. The reactor vessel 40 has an opening / closing section so that the fuel core 42 placed therein can be inserted and removed. The opening / closing section is, for example, a lid. The reactor vessel 40 can maintain a sealed state even when a nuclear reaction occurs therein and the inside becomes hot and high pressure. The reactor vessel 40 is also formed of a material with neutron shielding properties and is formed with a thickness that prevents neutrons generated inside from leaking to the outside. The reactor vessel 40 is formed of, for example, a metal. The reactor vessel 40 may contain a highly shielding element such as boron.

[0015] The core fuel 42 includes a plurality of fuel holding plates 43. A plurality of nuclear fuels are arranged inside the fuel holding plates 43. The fuel holding plates 43 are made of a material that transfers heat generated by the nuclear fuel. Graphite, silicon carbide, etc. can be used for the fuel holding plates 43. The core fuel 42 generates reaction heat as the nuclear fuel undergoes a nuclear reaction.

[0016] The control unit 44 has movable shielding materials between the core fuel 42. The shielding materials are so-called control rods that have the function of blocking radiation and suppressing nuclear reactions. The reactor 30 controls the reaction of the core fuel 42 by moving the control unit 44 and adjusting the position of the shielding materials.

[0017] 2, the heat conductive portion 32 is disposed inside the reactor vessel 40 and is in contact with the fuel holding plate 43. In this embodiment, the heat conductive portion 32 has a structure in which a plurality of plates are alternately stacked with the fuel holding plate 43. The heat conductive portion 32 is a plate having an outer shape larger than the fuel holding plate 43 and protrudes into an area where the fuel holding plate 43 is not disposed. Here, the heat conductive portion 32 may be made of, for example, titanium, nickel, copper, graphite, or graphene. In order to increase the efficiency of heat transfer to the protruding portion, the heat conductive portion 32 preferably uses graphene oriented in a direction that facilitates heat conduction along the surface of the plate. The heat conductive portion 32 transfers heat by solid-state thermal conduction. In other words, the heat conductive portion 32 transfers heat without using a heat medium (fluid). Specifically, the heat conductive portion 32 transfers heat generated in the core fuel 42 to the power generation unit 13 by solid-state thermal conduction.

[0018] The reactor unit 12 has the above configuration, and a nuclear reaction occurs in the core fuel 42 inside the reactor 30, generating reaction heat. The generated heat is accumulated inside the reactor vessel 40, causing the interior to become hot. In the reactor unit 12, a portion of the heat generated in the reactor 30 is transferred to the heat conduction section 32. The heat conduction section 32 heats the refrigerant flowing in the refrigerant circulation means 16 of the power generation unit 13. Here, carbon dioxide (CO2) is preferably used as the refrigerant.

[0019] The coolant circulation means 16 includes a circulation path 34 that circulates the coolant outside the reactor vessel 40 and a heat exchanger 36 that circulates the coolant inside the reactor vessel 40. The circulation path 34 and the heat exchanger 36 form a closed loop. The circulation path 34 circulates the coolant outside the reactor vessel 40 and is connected to the turbine 18, the cooler 22, the compressor 24, and the reheat exchanger 26. The heat exchanger 36 is inserted into the reactor vessel 40 and disposed inside. Both ends of the heat exchanger 36 are exposed to the outside of the reactor vessel 40 and connected to the circulation path 34. The heat exchanger 36 is a pipe through which the coolant flows and is in contact with the region of the heat conduction portion 32 that is not in contact with the core fuel 42. In other words, the heat exchanger 36 is in contact with the portion of the heat conduction portion 32 that protrudes beyond the core fuel 42. The heat exchanger 36 exchanges heat with the heat conduction portion 32 to heat the coolant. In this embodiment, the heat exchange section 36 and the heat conduction section 32 form the heat exchanger 14 .

[0020] The refrigerant flowing through the refrigerant circulation means 16 is supplied to the heat exchange section 36. The nuclear reactor power generation system 10 exchanges heat between the heat conduction section 32 and the refrigerant supplied from the refrigerant circulation means 16. The heat exchanger of this embodiment is composed of the heat conduction section 32 and the heat exchange section 36 of the refrigerant circulation means 16. The heat exchanger recovers heat from the heat conduction section 32 using the refrigerant flowing through the refrigerant circulation means 16. In other words, the refrigerant is heated in the heat conduction section 32. The heat medium heated in the heat exchange section 36 flows through the turbine 18, the cooler 22, the compressor 24, and the reheat exchanger 26 in this order. The refrigerant that has passed through the reheat exchanger 26 is supplied to the heat exchange section 36 again. In this manner, the refrigerant is circulated through the refrigerant circulation means 16.

[0021] The refrigerant that has passed through the heat exchanger 14 flows into the turbine 18. The turbine 18 is rotated by the energy of the heated refrigerant. In other words, the turbine 18 converts the energy of the refrigerant into rotational energy and absorbs energy from the refrigerant. The generator 20 is connected to the turbine 18 and rotates integrally with the turbine 18. The generator 20 generates electricity by rotating together with the turbine 18.

[0022] The cooler 22 cools the refrigerant that has passed through the turbine 18. The cooler 22 is a chiller, or a condenser in the case of temporarily liquefying the refrigerant. The compressor 24 is a pump that pressurizes the refrigerant. The reheat heat exchanger 26 exchanges heat between the refrigerant that has passed through the turbine 18 and the refrigerant that has passed through the compressor 24. The reheat heat exchanger 26 heats the refrigerant that has passed through the compressor 24 with the refrigerant that has passed through the turbine 18. In other words, the reheat heat exchanger 26 exchanges heat between the refrigerant before being cooled by the cooler 22 and the refrigerant after being cooled by the cooler 22, and recovers the heat that is discarded by the cooler 22 with the refrigerant before being supplied to the reactor unit 12.

[0023] In the nuclear power generation system 10, heat generated by the reaction of nuclear fuel in the nuclear reactor 12 is transferred to the refrigerant in the heat exchange unit 36 ​​via the heat transfer unit 32, and the heat from the heat transfer unit 32 heats the refrigerant flowing through the refrigerant circulation means 16. In other words, the refrigerant absorbs the heat transferred via the heat transfer unit 32. As a result, the heat generated in the nuclear reactor 12 is transferred via solid-state thermal conduction by the heat transfer unit 32 and recovered by the refrigerant. After being compressed by the compressor 24, the refrigerant is heated as it passes through the heat transfer unit 32, and the compressed energy is used to rotate the turbine 18. The refrigerant is then cooled to a reference state in the cooler 22 and supplied to the compressor 24 again.

[0024] As described above, the nuclear reactor power generation unit 10 transfers the heat of the nuclear reactor 30 to the coolant that serves as the medium for rotating the turbine 18 using the heat conduction section 32 that transfers heat by solid-state thermal conduction.

[0025] The nuclear reactor power generation unit 10 uses carbon dioxide as a refrigerant, thereby preventing contamination of the refrigerant even when the refrigerant is circulated inside the nuclear reactor 30. This reduces the risk of contamination of the medium that rotates the turbine 18. Furthermore, by providing a heat conduction section 32 that transfers heat by solid thermal conduction, the heat conduction section 32 can shield against neutron radiation.

[0026] Moreover, the reactor vessel 40 is preferably formed of a material having lower thermal conductivity than the heat conduction portion 32. This makes it possible to prevent the heat inside the reactor 30 from being discharged to the outside from portions other than the heat conduction portion 32, which is the path for discharging the heat to the outside.

[0027] Next, the reactor shielding facility 11 is arranged around the reactor power generation system 10. The reactor shielding facility 11 of this embodiment covers the side and top surfaces of the reactor power generation system 10, that is, all surfaces other than the installation surface 6. The reactor shielding facility 11 has a foundation structure 50, a shielding structure 52, a water tank 70, a polymer container 72, a water supply pipe 74, a polymer supply pipe 76, a moisture content detection unit 80, and a filling control unit 82.

[0028] The foundation structure 50 is a permanent structure made of concrete or the like. The foundation structure 50 is placed around the periphery of the nuclear reactor power generation system 10. The foundation structure 50 only needs to satisfy the strength requirements as a structure placed around the nuclear reactor 30. The foundation structure 50, as a structure around the nuclear reactor, can be formed of a material, thickness, etc. that does not satisfy the shielding performance.

[0029] The shielding structure 52 is a structure filled with water and polymers. In other words, the shielding structure 52 is composed of a structure with an empty space inside and the water and polymers filled inside the structure. The shielding structure 52 is placed on the outer surface of the foundation 50, that is, on the entire surface opposite the space in which the reactor 30 is located. The shielding structure 52, a structure with an empty space inside, can be made of various materials. The structure with an empty space inside can be made of metal, for example.

[0030] The polymer filled in the shielding structure 52 is a polymer processed material that absorbs water, that is, a polymer processed material that becomes a hydrate. Sodium polyacrylate can be used as the polymer. The shielding structure 52 may or may not have all of the water placed inside absorbed by the polymer.

[0031] The shielding structure 52 is a water-absorbed polymer or water that is disposed over the entire outer surface of the foundation 50 in a thickness that satisfies the shielding performance. The thickness of the shielding structure 52 varies depending on the design of the reactor 30 and the foundation 50, but it is preferable that the thickness of the foundation 50 and water be such that the radiation dose on the outer surface of the shielding structure 52 satisfies the statutory standards, for example.

[0032] The water tank 70 is a container filled with water. The polymer container 72 is a container filled with a polymer. The water supply pipe 74 connects the water tank 70 to the shielding structure 52. The shielding structure 52 has a connection part that connects to the water supply pipe 74. The connection part may have a structure that allows it to be attached and detached to the water supply pipe 74, and is closed with a lid or the like when the water supply pipe 74 is not connected. The polymer supply pipe 76 connects the polymer container 72 to the water supply pipe 74. The polymer supply pipe 76 supplies a polymer to the water supply pipe 74.

[0033] The moisture amount detection unit 80 detects the moisture amount in the shielding structure 52. The moisture amount detection unit 80 only needs to be able to detect the moisture amount in the shielding structure 52; for example, if the shielding structure 52 is filled with water, the water level can be used. The moisture amount detection unit 80 may detect the moisture amount using a hygrometer or the like. The moisture amount detection unit 80 may also measure the shape of the polymer using a distance sensor or the like to measure the amount of moisture held inside.

[0034] The filling control unit 82 controls the amount and timing of water and polymer to be supplied to the shielding structure 52 based on the detection results of the moisture amount detection unit 80. When the filling control unit 82 determines that the moisture amount is lower than the threshold value, it supplies water from the water tank 70 to the shielding structure 52.

[0035] Next, a method for manufacturing a reactor shielding system will be described with reference to FIG. 3. FIG. 3 is a schematic diagram showing an example of a method for manufacturing a reactor shielding system according to this embodiment. As shown in step S10, a nuclear power generation system 10 is installed on an installation surface 8. Next, as shown in step S12, a substructure 50 is installed around the nuclear power generation system 10. Next, as shown in step S14, a structure having a space disposed therein, which is part of a shielding structure 52, is created on the surface of the substructure 50. Next, as shown in step S16, water is supplied from a water tank 70 (arrow 80) while a polymer is supplied from a polymer container 72 (arrow 82), thereby filling the interior of the structure having a space disposed therein with water and a polymer. In this way, a shielding structure 52 filled with water and a polymer is created.

[0036] The reactor shielding facility 11 can appropriately shield the reactor 30 by disposing the shielding structure 52 over the entire outer surface of the foundation 50 and filling the inside of the shielding structure 52 with water and a polymer. Disposing the shielding structure 52 over the entire outer surface of the foundation 50 can prevent radiation from leaking through the gaps in the shielding structure 52. Furthermore, disposing the shielding structure 52 over the entire area not shielded by the ground can shield radiation using water. This allows the reactor shielding facility 11 to be constructed by filling it with water, thereby enabling easy construction. In other words, the reactor shielding facility 11 can be constructed without constructing or transporting solid materials with high shielding performance. Furthermore, when removing the facility, the portion providing the shielding function can be removed by removing the filled water and polymer.

[0037] 3, the reactor shielding system 11 supplies the polymer together with water to the hollow structure, but the order of supply is not limited to this. For example, the polymer may be supplied to the hollow structure first, and then water may be supplied.

[0038] The reactor shielding facility 11 can easily adjust the placement of liquid water by disposing a polymer inside the shielding structure 52. It can also suppress water leakage. It is preferable that the reactor shielding facility 11 is filled with a polymer, but it may also be filled with water in a liquid state.

[0039] The reactor shielding facility 11 of this embodiment is provided with a moisture content detection unit 80 and a filling control unit 82, thereby making it possible to adjust the moisture content inside the reactor shielding facility and maintain higher shielding performance, but is not limited to this, and a structure may be adopted in which no measurement or replenishment is performed. Also, a fixed amount of water may be replenished at predetermined intervals.

[0040] The reactor shielding facility 11 of this embodiment is configured to include the water tank 70, the polymer container 72, the water supply pipe 74, and the polymer supply pipe 76, but the reactor shielding facility 11 may also be configured without the water tank 70, the polymer container 72, the water supply pipe 74, and the polymer supply pipe 76. In other words, a mechanism for supplying water and polymer may be provided only during construction, and the shielding structure 52 may be constructed and then removed. This allows the mechanism for supplying water and polymer to be used for constructing multiple shielding structures 52.

[0041] Furthermore, the nuclear facility 1, as in this embodiment, has a reactor 30 that transfers heat from the core fuel by solid-state thermal conduction, making it a relatively small facility, and can suitably use a shielding structure that is easy to construct, such as the reactor shielding facility 11.

[0042] Fig. 4 is a schematic diagram showing another example of a reactor shielding system. The reactor shielding system may be configured by dividing the shielding structure into multiple compartments. In the shielding structure 52a shown in Fig. 4, the area outside the foundation structure 50 is divided into multiple compartments 202. Each compartment 202 is an enclosed space, and is partitioned by walls. The shielding structure 52a is divided into multiple compartments in both the thickness direction and the width direction.

[0043] By dividing the shielding structure 52a into multiple compartments 202, it is possible to fill each area with water and adjust the amount of water at each position (thickness in the shielding direction). The shielding structure 52a may be provided with connecting sections that supply water to each compartment 202, or may have a structure that connects the compartments 202 together. In the example shown in FIG. 4, the walls of the compartments 202 are aligned, but they may also be offset. This allows the positions of the walls that are not filled with water to be offset, thereby further improving the shielding performance.

[0044] Fig. 5 is a schematic diagram showing the overall configuration of a nuclear facility according to another embodiment. In the nuclear reactor facility shown in Fig. 5, the installation surface 6 of the nuclear power generation system 10 is formed underground 102 formed by digging into the ground 8. A reactor shielding facility 11b is placed on the upper surface of the nuclear power generation system 10. The lower and side surfaces of the nuclear power generation system 10 are shielded by the ground 8, and the upper surface is shielded by the reactor shielding facility 11b. The reactor shielding facility 11b serves as a lid for the underground 102. The reactor shielding facility 11b includes a foundation structure 50b and a shielding structure 52b.

[0045] In the nuclear facility 1b, the reactor 30 can be shielded by the ground 8 and the reactor shielding system 11b. In this way, when the reactor 30 is installed underground, the reactor shielding system 11b can be installed only on the top surface, which simplifies the structure.

[0046] In the nuclear facility 1 of this embodiment, all components of the reactor power generation system 10 are disposed in an area surrounded by the ground 8 and the reactor shielding facility 11, thereby enabling efficient placement of each component. Note that, in the nuclear facility 1, it is sufficient that the reactor having nuclear fuel is located in the area surrounded by the ground 8 and the reactor shielding facility 11, and other components may be placed outside the area surrounded by the ground 8 and the reactor shielding facility 11. In other words, it is sufficient that the reactor 30 is disposed in a space formed by the reactor shielding facility 11 surrounding the periphery of the reactor 30 and the installation surface 6, and each component of the power generation unit 13 may be placed outside the reactor shielding facility 11.

[0047] In this embodiment, the coolant circulation means 16 is inserted inside the reactor vessel 40, but the present invention is not limited to this. The heat conductive portion 32 that transfers heat by solid-state heat conduction may be configured to penetrate the reactor vessel 40 and protrude to the outside of the reactor vessel 40. [Explanation of symbols]

[0048] 1 Nuclear equipment 6 Installation surface 8 ground 10 Nuclear Power Systems 11 Reactor shielding equipment 12 Reactor Unit 13 Power Generation Unit 14 Heat exchanger 16 Refrigerant circulation means 18 Turbine 20. Generator 22 Chiller 24 Pump (compressor) 26 Regenerative heat exchanger 30 nuclear reactor 32 Heat conduction section 34 Circulation Route 36 Heat exchange section 40 Reactor vessel 42 Core fuel 43 Fuel holding plate 44 Control Unit 50 Foundation structures 52 Shielding Structure 70 Water Tank 72 Polymer container 74 Water supply pipe 76 Polymer supply pipe 80 Moisture content detector 82 Filling control unit

Claims

1. A reactor shielding system includes a reactor installed on an installation surface, a heat conduction unit that transfers heat generated in the reactor to the outside by solid-state heat conduction, and a power generation unit that generates power using the heat transferred by the heat conduction unit, a foundation structure disposed on the outer periphery of the reactor other than the installation surface and surrounding the entire surface of the reactor other than the installation surface; a shielding structure disposed on the entire surface of the foundation structure and filled with water.

2. 2. The reactor shielding system according to claim 1, wherein the shielding structure is disposed on a surface of the foundation opposite to the surface facing the reactor.

3. 3. The reactor shielding system according to claim 1, wherein the shielding structure contains a polymer compound capable of absorbing water therein.

4. 4. The reactor shielding system according to claim 1, wherein the shielding structure is a plurality of divided compartments.

5. 5. The reactor shielding system according to claim 1, wherein the shielding structure is a metal container filled with water.

6. 6. The reactor shielding system according to claim 1, wherein the shielding structure has a refilling mechanism that is openable and closable and that can supply water to the inside.

7. 7. The reactor shielding system according to claim 6, further comprising a tank connected to said replenishment mechanism for supplying water to said shielding structure.

8. A nuclear reactor and A nuclear facility comprising the reactor shielding system according to any one of claims 1 to 7.

9. the reactor is disposed on an installation surface formed vertically below the ground surface, The nuclear facility according to claim 8 , wherein the reactor shielding system is disposed on a surface above the reactor in the vertical direction.

10. 10. The nuclear facility according to claim 8, further comprising a power generation unit that is disposed in a space surrounded by the installation surface and the foundation, and generates electricity using heat generated in the nuclear reactor.

11. The nuclear reactor includes a solid core fuel and a reactor vessel that surrounds the core fuel, shields a space in which the core fuel is located, and shields against radiation, the power generation unit includes a heat conduction part disposed in at least a part of the reactor vessel and configured to conduct heat from within the reactor vessel to the outside by solid-state heat conduction; a heat exchanger that exchanges heat between the heat conduction portion and a refrigerant; a refrigerant circulation means for circulating the refrigerant passing through the heat exchanger; a turbine rotated by the refrigerant circulating in the refrigerant circulation means; The nuclear facility according to claim 10, further comprising: a generator that rotates integrally with the turbine.

12. a step of installing a foundation around a nuclear reactor installed on an installation surface, a heat conduction unit that transfers heat generated in the nuclear reactor to the outside by solid-state heat conduction, and a power generation unit that generates power using the heat transferred by the heat conduction unit; disposing a container across a surface of the substructure; and filling the vessel with water.

13. 13. The method for constructing a reactor shielding system according to claim 12, wherein a water-absorbing polymer compound is filled into the container together with the water.

14. 13. The method for constructing a reactor shielding system according to claim 12, further comprising the step of filling the container with a water-absorbing polymer compound before supplying the water.

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