Decay heat removal system for gas-cooled nuclear plant and gas-cooled nuclear reactor

Abstract

To provide a decay heat removal system for a gas-cooled nuclear plant and a gas-cooled nuclear reactor that can appropriately remove decay heat in an accident.SOLUTION: A gas-cooled nuclear plant is provided with: a reactor pressure vessel that accommodates a gas-cooled nuclear core; a reactor pressure vessel chamber that accommodates the reactor pressure vessel; a cooling panel that is provided in the reactor pressure vessel chamber to surround the periphery of the reactor pressure vessel; a thermoelectric element that is provided in the reactor pressure vessel chamber; and a fine particle reduction mechanism that is actuated by power generated in the thermoelectric element and reduces fine particles floating in the reactor pressure vessel chamber.SELECTED DRAWING: Figure 1

Description

[Technical Field]

[0001] FIELD OF THE INVENTION Embodiments of the present invention relate to gas-cooled nuclear power plants and gas-cooled reactor decay heat removal systems. [Background technology]

[0002] As shown in Figure 10, a gas-cooled reactor, for example, a high-temperature gas reactor, has cooling panels 4 for receiving radiant heat from the reactor pressure vessel 1, and exhaust ducts 5 and intake ducts 6 installed outside the cooling panels 4 between the reactor pressure vessel (RPV) 1 and the biological shield wall concrete 3 of the reactor pressure vessel room 2, and has a system for removing decay heat in the event of an accident by air flowing through the ducts. A steam generator 20 is provided in a confinement 17 outside the biological shield wall concrete 3, and a steam turbine 21 is connected to the steam generator 20. A double pipe 7 is also connected to the steam generator 20 from the reactor pressure vessel 1.

[0003] Decay heat removal systems for high-temperature gas-cooled reactors include not only the air-cooled systems mentioned above, but also systems such as the HTTR (Non-Patent Document 1) of the Japan Atomic Energy Agency, water-cooled systems such as those in Patent Document 1, and systems using heat pipes such as those in Patent Document 2. [Prior art documents] [Patent documents]

[0004] [Patent Document 1] Japanese Patent Application Publication No. 198789 / 1989 [Patent Document 2] Japanese Patent Application Publication No. 6-88893

[0005] [Non-Patent Document 1] http: / / www.aec.go.jp / / jicst / / NC / / iinkai / / teirei / / siryo2020 / / sireo11 / / 2_haif.pdf Summary of the Invention [Problem to be solved by the invention]

[0006] In the case of the decay heat removal system described above, whether it is water-cooled or air-cooled, in the event of an accident in which the primary coolant is lost from inside the reactor pressure vessel 1, for example, due to the rupture of the double pipe 7, the coolant, dust, etc. ejected from the reactor pressure vessel 1 at several tens of atmospheres will be scattered inside the reactor pressure vessel chamber 2, and fine particles on the order of microns or less will remain for a long time inside the reactor pressure vessel chamber 2. As a result, the scattering of radiant heat by the fine particles will reduce the radiation efficiency of the decay heat removal system, and there is a risk that the decay heat will not be removed properly.

[0007] In the case of a light water reactor, water can be sprayed from above the reactor pressure vessel 1 to allow small pieces to settle, but in the case of a gas-cooled reactor such as a high-temperature gas reactor, the temperature of the reactor pressure vessel 1 is much higher than in a light water reactor, so there is a risk of damage if water gets on high-temperature parts such as the reactor pressure vessel 1. Furthermore, if water seeps into the reactor pressure vessel 1, it will come into contact with the high-temperature graphite, which may cause a sudden heat generation and the generation of large amounts of gases such as carbon monoxide, carbon dioxide, and hydrogen.

[0008] Therefore, in the case of gas-cooled reactors such as high-temperature gas-cooled reactors, water cannot be sprayed. This also applies to systems that use water in the decay heat removal system, as shown in the above-mentioned publicly known examples, and the possibility of water entering the reactor pressure vessel due to damage to the cooling panels cannot be denied.

[0009] The present invention has been made in response to the above-mentioned conventional circumstances, and an object of the present invention is to provide a decay heat removal system for a gas-cooled nuclear plant and a gas-cooled nuclear reactor that can appropriately remove decay heat in the event of an accident. [Means for solving the problem]

[0010] A gas-cooled nuclear power plant according to an embodiment comprises a reactor pressure vessel that houses a gas-cooled core, a reactor pressure vessel chamber that houses the reactor pressure vessel, cooling panels that are provided within the reactor pressure vessel chamber so as to surround the reactor pressure vessel, a thermoelectric element that is provided within the reactor pressure vessel chamber, and a particulate reduction mechanism that is powered by electricity generated by the thermoelectric element and that reduces particulates floating within the reactor pressure vessel chamber.

[0011] The decay heat removal system for a gas-cooled reactor of one embodiment is a decay heat removal system for a gas-cooled reactor having a reactor pressure vessel that houses a gas-cooled core and a reactor pressure vessel chamber that houses the reactor pressure vessel, and is characterized by comprising: a cooling panel provided within the reactor pressure vessel chamber so as to surround the reactor pressure vessel; a thermoelectric element provided in the reactor pressure vessel chamber; and a particulate reduction mechanism that operates using electricity generated by the thermoelectric element and reduces particulates floating within the reactor pressure vessel chamber. [Effects of the Invention]

[0012] According to the embodiments of the present invention, it is possible to provide a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor that can appropriately remove decay heat in the event of an accident. [Brief explanation of the drawings]

[0013] [Figure 1] 1 is a diagram schematically showing the general configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a first embodiment. [Figure 2] FIG. 2 is a diagram schematically showing the AA cross-sectional configuration of FIG. 1. [Figure 3] FIG. 10 is a diagram schematically showing the general configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a second embodiment. [Figure 4] FIG. 10 is a diagram schematically showing the general configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a third embodiment. [Figure 5]FIG. 5 is a diagram schematically showing the AA cross-sectional configuration of FIG. 4. [Figure 6] FIG. 10 is a diagram schematically showing the general configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a fourth embodiment. [Figure 7] FIG. 10 is a diagram schematically showing the general configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a fifth embodiment. [Figure 8] FIG. 10 is a diagram schematically showing the schematic configuration of a cross section taken along the line AA of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a sixth embodiment. [Figure 9] FIG. 12 is a diagram schematically showing the general configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a seventh embodiment. [Figure 10] FIG. 1 is a diagram schematically showing the general configuration of a conventional gas-cooled nuclear power plant and a decay heat removal system for a gas-cooled nuclear reactor. DETAILED DESCRIPTION OF THE INVENTION

[0014] Hereinafter, a gas-cooled nuclear power plant and a decay heat removal system for a gas-cooled nuclear reactor according to an embodiment will be described with reference to the drawings.

[0015] (First embodiment) FIG. 1 is a diagram showing a schematic configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to the first embodiment, and FIG. 2 is a diagram showing a schematic configuration of the cross section AA in FIG. 1.

[0016] As shown in Fig. 1, a reactor pressure vessel (RPV) 1 containing a reactor core is housed in a reactor pressure vessel room 2. A biological shield wall concrete 3 is provided in the reactor pressure vessel room 2, and a steam generator 20 is provided in a confinement 17 outside the biological shield wall concrete 3, and a steam turbine 21 is connected to the steam generator 20. A double pipe 7 is connected from the reactor pressure vessel 1 to the steam generator 20.

[0017] As shown in Figure 2, cooling panels 4 are provided in the reactor pressure vessel room 2 so as to surround the reactor pressure vessel 1. An exhaust duct 5 and an intake duct 6 are connected to the cooling panels 4, and the cooling panels 4 are cooled by the gas circulated through these ducts.

[0018] An electrostatic precipitator 9 is provided as a particulate reduction mechanism between the reactor pressure vessel 1 and the cooling panel 4. A thermoelectric element 10 is placed on the top surface of the biological shield wall concrete 3 of the reactor pressure vessel room 2, and the thermoelectric element 10 and the electrostatic precipitator 9 are connected by an electric wire. As shown in Figure 2, the electrostatic precipitator 9 is positioned so that the positive electrode 15 and the negative electrode 16 face each other.

[0019] In the first embodiment having the above configuration, negatively charged particles from the discharge electrode, which is the negative electrode 16 of the electrostatic precipitator 9, are attracted to the collecting electrode, which is the positive electrode 15 of the electrostatic precipitator 9. Furthermore, the power for the electrostatic precipitator 9 is obtained from the thermoelectric element 10, which is activated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shield wall concrete 3. This enables the electrostatic precipitator 9 to collect particles floating in the reactor pressure vessel chamber 2, preventing a decrease in the radiation efficiency of the decay heat removal system using the cooling panel 4. Furthermore, even if the power supply is lost, decay heat can be reliably removed using the power obtained from the thermoelectric element 10.

[0020] (Second embodiment) Fig. 3 is a diagram showing a schematic configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a second embodiment. Note that parts corresponding to those of the first embodiment shown in Figs. 1 and 2 are given the same reference numerals, and duplicated explanations will be omitted.

[0021] 3, in the second embodiment, an exhaust fan 11, an exhaust duct 12 for the exhaust fan, an intake fan 13, and an intake duct 14 for the intake fan are arranged as particulate reduction mechanisms above the reactor pressure vessel room 2 and outside the biological shielding wall concrete 3. In addition, a thermoelectric element 10 is arranged on the top surface of the biological shielding wall concrete 3 of the reactor pressure vessel room 2, and the exhaust fan 11 and the intake fan 13 are connected to the thermoelectric element 10 by electric wires.

[0022] In the second embodiment having the above configuration, the exhaust fan 11 and the intake fan 13 are operated to suck in particles floating in the reactor pressure vessel room 2. The power for the exhaust fan 11 is obtained from the thermoelectric element 10, which is operated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shield wall concrete 3. This makes it possible to exhaust particles from the reactor pressure vessel room 2 and prevent a decrease in the radiation efficiency of the decay heat removal system using the cooling panel 4. Even if the power supply is lost, decay heat can be reliably removed using the power obtained from the thermoelectric element 10.

[0023] (Third embodiment) Fig. 4 is a diagram showing a schematic configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a third embodiment, and Fig. 5 is a diagram showing a schematic configuration of a cross section taken along line AA in Fig. 4. Note that parts corresponding to those of the first embodiment shown in Figs. 1 and 2 are given the same reference numerals, and duplicated explanations will be omitted.

[0024] As shown in Figures 4 and 5, in the third embodiment, the negative electrode 16 of the electrostatic precipitator 9 is placed between the reactor pressure vessel 1 and the cooling panel 4, the positive electrode 15 of the electrostatic precipitator 9 is placed on the surface of the cooling panel 4, and a thermoelectric element 10 is placed on the upper surface of the biological shielding wall concrete 3, and the electrostatic precipitator 9 and the thermoelectric element 10 are connected by an electric wire.

[0025] In the third embodiment of the above configuration, negatively charged particles are attracted to the positive electrode 15 of the collector electrode, which is the negative electrode 16 of the electrostatic precipitator 9 shown in FIG. 5. At this time, particles, including black graphite particles, gather on the surface of the cooling panel 4, improving the radiation efficiency of the cooling panel 4. The electrostatic precipitator 9 is powered by a thermoelectric element 10, which is activated by the temperature difference between its high-temperature side facing the reactor pressure vessel 1 and its low-temperature side grounded to the biological shield wall concrete 3. This allows for the collection of particles floating within the reactor pressure vessel chamber 2, preventing a decrease in the radiation efficiency of the decay heat removal system using the cooling panel 4 and improving the radiation efficiency of the cooling panel 4. Even in the event of a power outage, the electrostatic precipitator 9 can be operated using the power obtained from the thermoelectric element 10, ensuring reliable decay heat removal.

[0026] (Fourth embodiment) Fig. 6 is a diagram showing a schematic configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a fourth embodiment. Note that parts corresponding to those of the first embodiment shown in Figs. 1 and 2 are given the same reference numerals, and duplicated explanations will be omitted.

[0027] As shown in Fig. 6, in the fourth embodiment, an electric dust collector 9 is provided between the reactor pressure vessel 1 and the cooling panel 4. In addition, a thermoelectric element 10 is disposed on the upper surface of the biological shielding wall concrete 3, and the thermoelectric element 10 and the electric dust collector 9 are connected by an electric wire. The electric dust collector 9 is disposed so that the positive and negative poles face each other.

[0028] Additionally, an exhaust fan 11, an exhaust duct 12 for the exhaust fan, an intake fan 13, and an intake duct 14 for the intake fan are arranged at the top of the reactor pressure vessel room 2. The exhaust fan 11 and the intake fan 13 are connected by electric wires to thermoelectric elements 10 arranged on the top surface of the biological shielding wall concrete 3.

[0029] In the fourth embodiment having the above configuration, negatively charged fine particles of the discharge electrode, which is the negative electrode 16 of the electrostatic precipitator 9, are attracted to the positive electrode 15 of the electrostatic precipitator 9. The power source for the electrostatic precipitator 9 is obtained from a thermoelectric element 10, which is activated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shielding wall concrete 3.

[0030] Furthermore, operation of the exhaust fan 11 and intake fan 13 speeds up the movement of fine particles, making them more likely to collect at the electrostatic precipitator 9. The power for the exhaust fan 11 and intake fan 13 is obtained from a thermoelectric element 10, which is operated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shield wall concrete 3. This makes it possible to efficiently collect fine particles floating inside the reactor pressure vessel room 2 and prevent a decrease in the radiation efficiency of the decay heat removal system using the cooling panel 4. Furthermore, even if the power supply is lost, the electric power obtained from the thermoelectric element 10 can be used to operate the electrostatic precipitator 9, exhaust fan 11, and intake fan 13, ensuring reliable removal of decay heat.

[0031] (Fifth embodiment) Fig. 7 is a diagram showing a schematic configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a fifth embodiment. Note that parts corresponding to those of the first embodiment shown in Figs. 1 and 2 are given the same reference numerals, and duplicated explanations will be omitted.

[0032] As shown in FIG. 7, in the fifth embodiment, the negative electrode (discharge side) 16 of the electrostatic precipitator 9 is placed between the reactor pressure vessel 1 and the cooling panel 4, and the thermoelectric element 10 is placed on the upper surface of the biological shielding wall concrete 3, and they are connected by an electric wire.

[0033] In addition, a positive electrode (dust collection side) 15 of the electrostatic precipitator 9 is placed on the floor of the reactor pressure vessel chamber 2 and is connected to the thermoelectric element 10 by an electric wire. Furthermore, an exhaust fan 11, an exhaust duct 12 for the exhaust fan, an intake fan 13, and an intake duct 14 for the intake fan are placed below the reactor pressure vessel 1 in the reactor pressure vessel chamber 2. The exhaust fan 11 and the intake fan 13 are connected to the thermoelectric element 10 by an electric wire.

[0034] In the fifth embodiment having the above configuration, the fine particles are negatively charged at the discharge electrode, which is the negative electrode 16 of the electrostatic precipitator 9. The power source for the electrostatic precipitator 9 is obtained from a thermoelectric element 10, which is activated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shielding wall concrete 3.

[0035] Furthermore, the operation of the exhaust fan 11 and intake fan 13 speeds up the movement of the fine particles, making them more likely to gather at the positive electrode 15 of the electrostatic precipitator 9 placed on the floor. The power for the exhaust fan 11 and intake fan 13 is obtained from a thermoelectric element 10, which is activated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shielding wall concrete 3.

[0036] This makes it possible to efficiently collect particles inside the reactor pressure vessel room 2 and prevent a decrease in the radiation efficiency of the decay heat removal system using the cooling panels 4. Furthermore, even if the power supply is lost, the electric power obtained from the thermoelectric elements 10 can be used to operate the electrostatic precipitator 9, exhaust fan 11, and intake fan 13, ensuring reliable removal of decay heat.

[0037] (Sixth embodiment) Fig. 4 is a diagram schematically showing the configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a sixth embodiment, and Fig. 8 is a diagram schematically showing the configuration of the cross section AA in Fig. 4. Note that parts corresponding to those of the first embodiment shown in Figs. 1 and 2 are given the same reference numerals, and duplicated explanations will be omitted.

[0038] As shown in Figures 4 and 8, in the sixth embodiment, the negative electrode (discharge side) of the electrostatic precipitator 9 is disposed between the reactor pressure vessel 1 and the cooling panel 4, the positive electrode 15 of the electrostatic precipitator 9 is disposed on the surface of the cooling panel 4, and the thermoelectric element 10 is disposed on the upper surface of the biological shielding wall concrete 3, and they are connected by electric wires. In addition, the positive electrodes 15 of the electrostatic precipitator 9 are disposed in a mottled manner on the surface of the cooling panel 4. That is, the positive electrodes 15 of the electrostatic precipitator 9 are not disposed uniformly on the surface of the cooling panel 4 as in the third embodiment, but are disposed at intervals. The only difference from the third embodiment is that the positive electrodes 15 of the electrostatic precipitator 9 are disposed in a mottled manner.

[0039] In the sixth embodiment having the above configuration, negatively charged particles at the discharge electrode, which is the negative electrode 16 of the electrostatic precipitator 9 in Fig. 8, are attracted to the positive electrode 15 of the electrostatic precipitator 9. At this time, particles including black graphite particles gather more densely on the surface of the cooling panel 4 than in the third embodiment, further improving the radiation efficiency of the cooling panel 4. In addition, the power source for the electrostatic precipitator 9 is obtained from a thermoelectric element 10, which is operated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shielding wall concrete 3.

[0040] This makes it possible to efficiently collect particles floating inside the reactor pressure vessel chamber 2, preventing a decrease in the radiation efficiency of the decay heat removal system using the cooling panels 4 and improving the radiation efficiency of the cooling panels 4. Furthermore, even if the power supply is lost, the electric power obtained from the thermoelectric elements 10 can be used to operate the electrostatic precipitator 9, ensuring reliable removal of decay heat.

[0041] Seventh embodiment Fig. 9 is a diagram showing a schematic configuration of a gas-cooled nuclear plant and a decay heat removal system for a gas-cooled nuclear reactor according to a seventh embodiment. Note that parts corresponding to those of the first embodiment shown in Figs. 1 and 2 are given the same reference numerals, and duplicated explanations will be omitted.

[0042] 9, in the seventh embodiment, an electrostatic precipitator 9 is placed in a confinement 17, and a thermoelectric element 10 is placed on the upper surface of the biological shield wall concrete 3 above the reactor pressure vessel 1, and they are connected by electric wires. The electrostatic precipitator 9 is placed so that the positive and negative poles face each other.

[0043] 9, an exhaust fan 11, an exhaust duct 12 for the exhaust fan, an intake fan 13, and an intake duct 14 for the intake fan are arranged for ventilation between the reactor pressure vessel room 2 and the confinement 17. The exhaust fan 11, the intake fan 13, and the thermoelectric element 10 are connected by electric wires to the thermoelectric element 10 arranged on the top surface of the biological shielding wall concrete 3. The confinement 17 is also provided with an exhaust duct 12 for exhausting air to the outside.

[0044] In the seventh embodiment having the above configuration, fine particles moved from the reactor pressure vessel chamber 2 to the confinement 17 by the exhaust fan 11 are attracted to the electrostatic precipitator 9. The power for the electrostatic precipitator 9 is obtained from a thermoelectric element 10, which is activated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shielding wall concrete 3. The power for the exhaust fan 11 and the intake fan 13 is obtained from the thermoelectric element 10, which is activated by the temperature difference between the high-temperature side facing the reactor pressure vessel 1 and the low-temperature side grounded to the biological shielding wall concrete 3.

[0045] In the seventh embodiment, even when the temperature inside the reactor pressure vessel chamber 2 becomes too high to use the electrostatic precipitator 9, it is possible to efficiently collect particles inside the reactor pressure vessel chamber 2, and it is possible to prevent a decrease in the radiation efficiency of the decay heat removal system using the cooling panel 4. Furthermore, even when the power supply is lost, it is possible to operate the electrostatic precipitator 9, exhaust fan 11, and intake fan 13 using the power obtained from the thermoelectric element 10, and it is possible to reliably remove decay heat. Furthermore, it is possible to collect particles to which FPs such as iodine in the leaked primary coolant are attached, which can contribute to reducing the radiation dose inside the reactor pressure vessel chamber 2 after an accident.

[0046] Although several embodiments of the present invention have been described above, these embodiments are presented as examples and are not intended to limit the scope of the invention. These novel embodiments can be embodied in various other forms, and various omissions, substitutions, modifications, and combinations can be made without departing from the spirit of the invention. These embodiments and their modifications are included within the scope and spirit of the invention, and are also included in the scope of the invention and its equivalents as defined in the claims. [Explanation of symbols]

[0047] 1...Reactor pressure vessel, 2...Reactor pressure vessel room, 3...Biological shield wall concrete, 4...Cooling panel, 5...Exhaust duct, 6...Intake duct, 7...Double pipe, 9...Electrostatic precipitator, 10...Thermoelectric element, 11...Exhaust fan, 12...Exhaust duct for exhaust fan, 13...Intake fan, 14...Intake duct for intake fan, 15...Positive electrode (dust collection side) of electrostatic precipitator, 16...Negative electrode (discharge side) of electrostatic precipitator, 17...Confinement, 20...Steam generator, 21...Steam turbine.

Claims

1. a reactor pressure vessel containing a gas-cooled reactor core; a reactor pressure vessel chamber that houses the reactor pressure vessel; a cooling panel provided in the reactor pressure vessel chamber so as to surround the reactor pressure vessel; a thermoelectric element provided in the reactor pressure vessel chamber; a particulate reduction mechanism that operates using the electric power generated by the thermoelectric element and reduces particulates floating in the reactor pressure vessel chamber; A gas-cooled nuclear power plant comprising:

2. 2. The gas-cooled nuclear power plant according to claim 1, The particulate reduction mechanism includes an electrostatic precipitator provided in the reactor pressure vessel chamber outside the reactor pressure vessel. A gas-cooled nuclear power plant.

3. 3. The gas-cooled nuclear power plant according to claim 1, The particulate reduction mechanism includes an exhaust duct and an exhaust fan that exhaust air from the reactor pressure vessel chamber, and an intake duct and an intake fan that draw air into the reactor pressure vessel chamber. A gas-cooled nuclear power plant.

4. 3. The gas-cooled nuclear power plant according to claim 2, The dust collection side electrode of the electrostatic precipitator is disposed on the cooling panel on the side facing the reactor pressure vessel. A gas-cooled nuclear power plant.

5. 3. The gas-cooled nuclear power plant according to claim 2, The electrodes on the dust collection side of the electrostatic precipitator are arranged in a mottled manner on the cooling panel on the side facing the reactor pressure vessel. A gas-cooled nuclear power plant.

6. 3. The gas-cooled nuclear power plant according to claim 2, The discharge electrode of the electrostatic precipitator is disposed on the side of the reactor pressure vessel, and the dust collection side of the electrostatic precipitator is disposed on the floor of the reactor pressure vessel room. A gas-cooled nuclear power plant.

7. 7. The gas-cooled nuclear power plant according to claim 6, Below the reactor pressure vessel in the reactor pressure vessel room, An exhaust duct and an exhaust fan for exhausting air from the reactor pressure vessel chamber, and an intake duct and an intake fan for drawing air into the reactor pressure vessel chamber are provided. A gas-cooled nuclear power plant.

8. 3. The gas-cooled nuclear power plant according to claim 2, The electrostatic precipitator is disposed within a confinement; An exhaust duct and an exhaust fan are provided between the reactor pressure vessel chamber and the confinement, and the exhaust fan is driven by the electric power generated by the thermoelectric element. A gas-cooled nuclear power plant.

9. a reactor pressure vessel containing a gas-cooled reactor core; a reactor pressure vessel chamber that houses the reactor pressure vessel; A decay heat removal system for a gas-cooled nuclear reactor, comprising: a cooling panel provided in the reactor pressure vessel chamber so as to surround the reactor pressure vessel; a thermoelectric element provided in the reactor pressure vessel chamber; a particulate reduction mechanism that operates using the electric power generated by the thermoelectric element and reduces particulates floating in the reactor pressure vessel chamber; A decay heat removal system for a gas-cooled nuclear reactor, comprising:

10. 10. The decay heat removal system for a gas-cooled nuclear reactor according to claim 9, The particulate reduction mechanism includes an electrostatic precipitator provided in the reactor pressure vessel chamber outside the reactor pressure vessel. A decay heat removal system for a gas-cooled nuclear reactor.

11. The decay heat removal system for a gas-cooled nuclear reactor according to claim 9 or 10, The particulate reduction mechanism includes an exhaust duct and an exhaust fan that exhaust air from the reactor pressure vessel chamber, and an intake duct and an intake fan that draw air into the reactor pressure vessel chamber. A decay heat removal system for a gas-cooled nuclear reactor.

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