Nuclear system

Abstract

To reduce monitoring cost in a nuclear system.SOLUTION: A nuclear system comprises: a nuclear reactor core; a heat conductor that conducts heat which is generated by nuclear reaction of nuclear fuel in the nuclear reactor core to outside by means of a cooling medium; a reactivity control device that has a plurality of control drums in which a neutron absorption part arranged outside the nuclear reactor core to absorb neutrons is provided; a state detector that detects an operational state of a nuclear reactor; and an analysis unit that reproduces the operation state of the nuclear reactor in a virtual space using a virtual model of the nuclear reactor on the basis of a detection result of the state detector.SELECTED DRAWING: Figure 3

Description

[Technical Field]

[0001] The present disclosure relates to nuclear power systems. [Background technology]

[0002] A nuclear power generation system has a nuclear reactor that stores nuclear fuel. In the nuclear power generation system, a nuclear reaction occurs in the nuclear reactor using the nuclear fuel, and the generated heat is extracted to the outside to heat a refrigerant. The heated refrigerant drives a turbine to rotate, thereby generating electricity using a generator. An example of such a nuclear power generation system is described in Patent Document 1. [Prior art documents] [Patent documents]

[0003] [Patent Document 1] Patent No. 7426323 Summary of the Invention [Problem to be solved by the invention]

[0004] The nuclear reactor described in Patent Document 1 is an ultra-small nuclear reactor, known as a microreactor. Microreactors are small enough to be transported by truck or other means, making them highly portable. Microreactors also differ from light water reactors in some ways. That is, while light water reactors use light water as a coolant and moderator, the microreactor described in Patent Document 1 does not use light water. In a microreactor, heat generated by nuclear fission in the reactor core is transferred to heat transfer tubes via a thermal conductor, heating the cooling medium flowing inside the heat transfer tubes. Such microreactors are controlled differently from light water reactors, and there is a demand for reduced-cost monitoring and control.

[0005] The present disclosure is intended to solve the above-mentioned problems, and aims to provide a nuclear power system that reduces monitoring costs. [Means for solving the problem]

[0006] In order to achieve the above-mentioned object, the nuclear power system of the present disclosure includes a reactor core, a thermal conductor that conducts heat generated by the nuclear reaction of nuclear fuel in the reactor core to the outside using a cooling medium, a reactivity control device that is arranged outside the reactor core and has a plurality of control drums that are provided with neutron absorption units that absorb neutrons, a status detector that detects the operating status of the reactor, and an analysis unit that reproduces the operating status of the reactor in a virtual space using a virtual model of the reactor based on the detection results of the status detector. [Effects of the Invention]

[0007] According to the nuclear power system of the present disclosure, it is possible to reduce monitoring costs. [Brief explanation of the drawings]

[0008] [Figure 1] FIG. 1 is a schematic diagram showing a nuclear power generation system according to this embodiment. [Figure 2] FIG. 2 is a cross-sectional view showing the reactor unit of this embodiment. [Figure 3] FIG. 3 is a block diagram showing the nuclear power system of this embodiment. DETAILED DESCRIPTION OF THE INVENTION

[0009] Preferred embodiments of the present disclosure will be described in detail below with reference to the drawings. Note that the present disclosure is not limited to these embodiments, and when there are multiple embodiments, the present disclosure also includes configurations that combine the embodiments. Furthermore, the components in the embodiments include those that can be easily imagined by a person skilled in the art, those that are substantially identical, and those that are within the so-called equivalent range.

[0010] <Nuclear power generation system> FIG. 1 is a schematic diagram showing a nuclear power generation system according to this embodiment.

[0011] As shown in FIG. 1, the nuclear power generation system 100 includes a reactor unit 101, a refrigerant circulation path 102, a turbine 103, a compressor 104, a generator 105, a heat exchanger 106, and a cooler 107.

[0012] The reactor unit 101 has a reactor vessel 111, a reactor 112, and a heat transfer tube section 113. The reactor vessel 111 houses the reactor 112 inside. The reactor vessel 111 houses the reactor 112 in a sealed state. The reactor vessel 111 is provided with an opening and closing section, such as a lid, so that the reactor 112 placed inside can be stored or removed. The reactor vessel 111 can maintain a sealed state even when a nuclear reaction occurs in the reactor 112 and the inside becomes hot and high pressure. The reactor vessel 111 is made of a material with thermal insulation properties.

[0013] The reactor 112 stores nuclear fuel. The reactor 112 causes a nuclear reaction in the nuclear fuel to generate heat. The heat transfer tube section 113 extracts the heat generated in the reactor 112 to the outside. Details of the reactor vessel 111, the reactor 112, and the heat transfer tube section 113 will be described later.

[0014] The refrigerant circulation path 102 is a path for circulating the cooling medium. The refrigerant circulation path 102 connects the reactor unit 101 to the turbine 103, heat exchanger 106, cooler 107, compressor 104, and heat exchanger 106 in this order in the flow direction of the cooling medium, and is then connected back to the reactor unit 101. The high-temperature cooling medium extracted from the reactor unit 101 flows through the refrigerant circulation path 102, passes through the turbine 103, heat exchanger 106, cooler 107, compressor 104, and heat exchanger 106 in this order, and returns to the reactor unit 101.

[0015] The turbine 103 and the compressor 104 are connected by a connecting shaft 108 and are rotatable integrally. The compressor 104 is connected to a generator 105 by a connecting shaft 109, and the driving torque of the turbine 103 and the compressor 104 is transmitted to the generator 105. The turbine 103 is driven to rotate by the cooling medium heated by the reactor unit 101 and transmits the driving torque to the compressor 104. The compressor 104 is driven to rotate by the driving torque transmitted from the turbine 103 via the connecting shaft 108, and compresses the cooling medium cooled by the cooler 107. The generator 105 is driven by the driving torque transmitted from the compressor 104 via the connecting shaft 109 to generate electricity.

[0016] The heat exchanger 106 exchanges heat between the cooling medium that has been heated by the reactor unit 101 and then driven the turbine 103 and the cooling medium that has driven the compressor 104 .

[0017] The cooler 107 cools the cooling medium that has been subjected to heat exchange in the heat exchanger 106 after driving the turbine 103. The cooler 107 cools the cooling medium by exchanging heat between the cooling medium flowing through the refrigerant circulation path 102 and a secondary cooling medium.

[0018] Heat generated by the reaction of nuclear fuel in the nuclear reactor 112 is extracted via the heat transfer tube section 113. That is, the heat transfer tube section 113 heats the cooling medium with the heat of the nuclear reactor 112 and causes the high-temperature cooling medium to flow through the refrigerant circulation path 102. The cooling medium flowing through the refrigerant circulation path 102 is supplied to the turbine 103.

[0019] The turbine 103 is driven to rotate by the cooling medium flowing through the refrigerant circulation path 102, and transmits the driving rotation force to the compressor 104. The cooling medium that has driven the turbine 103 flows through the heat exchanger 106 to the cooler 107 and is cooled. The cooling medium cooled by the cooler 107 is supplied to the compressor 104. The compressor 104 is driven to rotate by the driving rotation force transmitted from the turbine 103 via the connecting shaft 108, and compresses the cooling medium supplied from the cooler 107.

[0020] At this time, the generator 105 is driven by the driving torque transmitted from the compressor 104 via the connecting shaft 109 to generate electricity.

[0021] The cooling medium that has driven the compressor 104 is supplied to the heat exchanger 106. The heat exchanger 106 exchanges heat between the cooling medium that has driven the turbine 103 and the cooling medium that has driven the compressor 104. That is, the heat exchanger 106 heats the low-temperature cooling medium that has driven the compressor 104 with the high-temperature cooling medium that has driven the turbine 103.

[0022] The cooling medium heated by the heat exchanger 106 is then returned to the reactor 112 .

[0023] The nuclear power generation system 100 extracts heat from a nuclear reactor 112 using a cooling medium through a heat transfer tube section 113, drives a turbine 103 with the high-temperature, high-pressure cooling medium, and generates electricity using a generator 105.

[0024] <Reactor Unit> FIG. 2 is a cross-sectional view showing the reactor unit of this embodiment.

[0025] 2, the reactor unit 101 has a reactor vessel 111, a reactor 112, and a heat transfer tube section 113. The reactor 112 is housed inside the reactor vessel 111, and is provided with the heat transfer tube section 113. The heat transfer tube section 113 extracts heat generated in the reactor 112 to the outside.

[0026] <Reactor> The reactor 112 has a reactor core (reactor core) 11, and is provided with a reflector 12, a thermal conductor 13, and a reactivity control device 14. The reactor 112 is arranged horizontally. That is, the reactor 112 is arranged with its central axis O aligned horizontally. However, the reactor 112 may also be arranged vertically. That is, the reactor 112 may be arranged with its central axis O aligned vertically.

[0027] <Reactor Core> The core 11 has multiple fuel blocks, and the fuel blocks are configured by storing fissile materials such as uranium (e.g., uranium-235), plutonium (e.g., plutonium-239, plutonium-241), and thorium inside a support such as highly oriented graphite (graphite) containing graphene.

[0028] <Reflector> The reflector 12 is arranged to surround the reactor core 11. The reflector 12 is made of a graphite block and has the ability to scatter and absorb neutrons of the radiation (neutrons) emitted from the nuclear fuel that constitutes the reactor core 11.

[0029] The reflector 12 has a body 31 and a pair of wall portions 32, 33. The body 31 is cylindrical and is disposed radially outside the core 11. That is, the body 31 covers the outer periphery of the core 11 so as to surround it. The wall portion 32 is disk-shaped and is disposed on one axial side of the body 31. That is, the wall portion covers and closes one end of the core 11. The wall portion 33 is disk-shaped and is disposed on the other axial side of the body 31. That is, the wall portion 33 covers and closes the other end of the core 11.

[0030] The reactor vessel 111 has a body portion 34, support plates 35 and 36, and lid portions 37 and 38. The body portion 34 is cylindrical and disposed radially outside the reflector 12. That is, the body portion 34 surrounds and covers the outer periphery of the reflector 12. The support plate 35 is disk-shaped and disposed on one axial side of the body portion 34. That is, the support plate 35 covers and closes one end of the reflector 12. The support plate 36 is disk-shaped and disposed on the other axial side of the body portion 34. That is, the support plate 36 covers and closes the other end of the core 11. The lid portion 37 is hemispherical and disposed on one axial side of the body portion 34. That is, the lid portion 37 is attached so as to cover the support plate 35. The lid portion 38 is hemispherical and disposed on the other axial side of the body portion 34. That is, the lid portion 38 is attached so as to cover the support plate 36 .

[0031] <Thermal conductor> The heat transfer tube section 113 has a heat conductor 13. The heat conductor 13 has heat transfer tubes 41. That is, the heat conductor 13 transfers heat generated by the nuclear reaction of the nuclear fuel in the core 11 to the heat transfer tubes 41. The heat conductor 13 is provided with an inlet side manifold 42, an outlet side manifold 43, an inlet pipe 44, and an outlet pipe 45 for the heat transfer tubes 41.

[0032] The heat transfer tubes 41 are arranged on the outer periphery or the center of the reactor core 11. A plurality of heat transfer tubes 41 are arranged so as to surround the entire periphery of the reactor core 11 from the outside. A plurality of heat transfer tubes 41 are arranged so as to surround the reactor core 11 from the inside.

[0033] The plurality of heat transfer tubes 41 are arranged to penetrate the reactor core 11 in the axial direction. One longitudinal end of each of the plurality of heat transfer tubes 41 is supported by the support plate 35, and the other longitudinal end is supported by the support plate 36. The inlet-side manifold 42 is arranged outside the support plate 35. One ends of the plurality of heat transfer tubes 41 are connected to the inlet-side manifold 42. The outlet-side manifold 43 is arranged outside the support plate 36. The other ends of the plurality of heat transfer tubes 41 are connected to the outlet-side manifold 43. One end of the inlet pipe 44 is connected to the inlet-side manifold 42, and the other end passes through the lid 37 and extends to the outside. The outlet pipe 45 is connected to the outlet-side manifold 43, and the other end passes through the lid 38 and extends to the outside.

[0034] The cooling medium is supplied from an inlet pipe 44 to an inlet-side manifold 42, and flows from the inlet-side manifold 42 to a plurality of heat transfer tubes 41. The cooling medium flows through each heat transfer tube 41 and is discharged to an outlet-side manifold 43, and is then discharged from the outlet-side manifold 43 through an outlet pipe 45. At this time, as the cooling medium flows through the plurality of heat transfer tubes 41, it is heated by the heat generated by the nuclear reaction of the nuclear fuel in the reactor core 11, and the heat is taken out to the outside.

[0035] <Reactivity Control Device> The reactivity control device 14 is disposed in the reflector 12. The reactivity control device 14 is disposed so as to surround the periphery of the reactor core 11. The reactivity control device 14 has a plurality of control drums 51. The plurality of control drums 51 are disposed outside the reactor core 11 at intervals (preferably at equal intervals) in the circumferential direction. The plurality of control drums 51 are disposed facing each other outside the reactor core 11.

[0036] The control drum 51 has a cylindrical shape and is arranged along the axial direction of the core 11. The control drum 51 has approximately the same length as the core 11. The control drum 51 is rotatably supported by the reflector 12. A connecting part 52 is connected to one axial end of the control drum 51. The connecting part 52 penetrates the support plate 35 and the lid part 37 of the reflector 12, and one end is connected to one end of the control drum 51 and the other end extends outside the reflector 12. The driving part 53 is arranged outside the reactor 112. The other ends of the multiple connecting parts 52 are connected to the driving part 53. The driving part 53 can rotate the multiple control drums 51 via the multiple connecting parts 52.

[0037] The control drum 51 has a drum main body and a neutron absorbing portion. The control drum 51 is configured such that the neutron absorbing portion is provided on a part of the drum main body in the circumferential direction. The neutron absorbing portion has higher neutron absorption performance than the drum main body and the reflector 12.

[0038] The circumferential position of the neutron absorbing portion on the drum body changes as the control drum 51 rotates. That is, as the control drum 51 rotates, the neutron absorbing portion can move closer to or farther away from the reactor core 11.

[0039] The reactivity control device 14 has a control unit 57. The control unit 57 is connected to the drive unit 53. The control unit 57 can control the rotational positions of the multiple control drums 51 by controlling the drive unit 53. The control unit 57 is a controller, and is realized by, for example, a CPU (Central Processing Unit) or an MPU (Micro Processing Unit) executing various programs stored in the storage unit using RAM as a work area.

[0040] <Nuclear Power Systems> FIG. 3 is a block diagram showing the nuclear power system of this embodiment.

[0041] As shown in FIG. 3, the nuclear power system 60 includes a reactor unit 101, a state detector 61, a control device 62, an operation unit 63, a display unit 64, and a storage unit 65.

[0042] As described above, the reactor unit 101 has a reactor vessel 111, a reactor 112, and a heat transfer tube section 113, and the reactor 112 has a core 11, a reflector 12, a heat conductor 13, and a reactivity control device 14.

[0043] The state detector 61 detects the operating state of the nuclear reactor 112. The state detector 61 includes a temperature detector 71, a flow rate detector 72, a pressure detector 73, and a neutron flux detector 74.

[0044] 2, a temperature detector 71 is provided in the inlet pipe 44 and detects the inlet gas temperature of the cooling medium introduced into the heat transfer tubes 41 of the thermal conductor 13. A flow rate detector 72 is provided in the inlet pipe 44 and detects the inlet gas flow rate of the cooling medium introduced into the heat transfer tubes 41 of the thermal conductor 13. A pressure detector is provided in the outlet pipe 45 and detects the outlet gas pressure of the cooling medium discharged from the heat transfer tubes 41 of the thermal conductor 13. A plurality of neutron flux detectors 74 are provided around the reactor core and detect neutron flux in the reactor core 11.

[0045] 3, the temperature detector 71, the flow rate detector 72, the pressure detector 73, and the neutron flux detector 74 are connected to the control device 62. The temperature detector 71, the flow rate detector 72, the pressure detector 73, and the neutron flux detector 74 output the detected inlet gas temperature, inlet gas flow rate, outlet gas pressure, and neutron flux to the control device 62.

[0046] The control device 62 has an analysis unit 81 and a control unit 82. The control device 62 is a controller, and is realized by, for example, a CPU (Central Processing Unit) or an MPU (Micro Processing Unit) executing various programs stored in the storage unit 65 using RAM as a work area. The analysis unit 81 and the control unit 82 in the control device 62 may be multiplexed.

[0047] The analysis unit 81 reproduces the operating state of the reactor 112 in a virtual space using a virtual model of the reactor 112 based on the detection results of the state detector 61. Specifically, the analysis unit 81 reproduces the operating state of the reactor 112 in a virtual space using a neutron transport equation, gas continuity equation, kinetic equation, and energy equation, and core heat conduction equation based on the inlet gas temperature, inlet gas flow rate, outlet gas pressure, and neutron flux, and outputs the core power distribution, core temperature distribution, and core outlet gas temperature distribution.

[0048] The reactor 112 of this embodiment is an ultra-small reactor, also known as a microreactor. Microreactors are different from light water reactors. While light water reactors use light water as a coolant and moderator, microreactors do not use light water. Instead, heat generated by nuclear fission in the reactor core 11 is transferred to a cooling medium via a thermal conductor 13, and is then removed to the outside via the heated cooling medium. The analysis unit 81 uses digital twin technology to simulate a virtual model of the reactor 112, known as a microreactor, to reproduce the core conditions of the reactor 112 in a virtual space, outputting and enabling monitoring of the core power distribution, core temperature distribution, and core outlet gas temperature distribution.

[0049] The control unit 82 controls the reactor 112 based on the analysis results of the analysis unit 81. Specifically, the control unit 82 controls the reactor 112 based on the operating state of the reactor 112 reproduced in the virtual space by the analysis unit 81. The control unit 82 includes a control unit 57 of the reactivity control device 14, and controls the reactivity control device 14, that is, the drive unit 53.

[0050] The operation unit 63 is connected to the control device 62. The operation unit 63 can be operated by an operator and outputs an operation command signal to the control device 62. The display unit 64 is connected to the control device 62. The display unit 64 is, for example, a display, and displays the contents processed by the control device 62. The operator can monitor the core status of the reactor 112 displayed on the display unit 64, that is, the core power distribution, the core temperature distribution, the core outlet gas temperature distribution, etc. The memory unit 65 is connected to the control device 62. The memory unit 65 stores various programs executed by the control device 62.

[0051] The memory unit 65 also stores the inlet gas temperature, inlet gas flow rate, outlet gas pressure, and neutron flux input to the control device 62 from the temperature detector 71, flow rate detector 72, pressure detector 73, and neutron flux detector 74. The memory unit 65 also stores the core power distribution, core temperature distribution, and core outlet gas temperature distribution analyzed by the analysis unit 81.

[0052] <Controller processing> As shown in FIGS. 2 and 3 , the control unit 82 controls the drive unit 53 of the reactivity control device 14. The reactivity control device 14 controls the reactor core 11 by rotating the control drum 51 with the drive unit 53. When the control drum 51 is positioned such that the neutron absorbing portion does not face the reactor core 11, neutrons emitted from the reactor core 11 to the outside are not absorbed by the control drum 51 and contribute to nuclear fission. This increases the reactivity of the nuclear fuel constituting the reactor core 11. On the other hand, when the control drum 51 is positioned such that the neutron absorbing portion faces the reactor core 11, neutrons emitted from the reactor core 11 to the outside are absorbed by the neutron absorbing portion of the control drum 51 and do not contribute to nuclear fission. This decreases the reactivity of the nuclear fuel constituting the reactor core 11. The reactivity control device 14 can control the reactivity of the nuclear fuel in the reactor core 11 by rotating multiple control drums 51.

[0053] The analysis unit 81 reproduces the operating state of the reactor 112 in a virtual space using a virtual model of the reactor 112 based on the detection results of the state detector 61. The analysis unit 81 outputs the core power distribution, core temperature distribution, core outlet gas temperature distribution, etc. according to the operating state of the reactor 112 in the virtual space and displays them on the display unit 64. The operator can view and monitor the core power distribution, core temperature distribution, core outlet gas temperature distribution, etc. displayed on the display unit 64. The control unit 82 also monitors the core power distribution, core temperature distribution, core outlet gas temperature distribution, etc. output by the analysis unit 81.

[0054] Furthermore, the control unit 82 controls the reactor 112 based on the core power distribution, core temperature distribution, core outlet gas temperature distribution, etc. output by the analysis unit 81. In other words, the control unit 82 controls the drive unit 53 via the reactivity control device 14 so that the core power distribution, core temperature distribution, and core outlet gas temperature distribution output by the analysis unit 81 are maintained within predetermined ranges.

[0055] A typical pressurized water reactor, a type of light water reactor, has 20 to 60 thermocouples installed in the reactor, and the control unit acquires the core temperature and other data based on the measurement results of the numerous thermocouples. The control unit also monitors the reactor's operating state based on the core inlet and outlet temperatures of the primary coolant and the neutron flux in the core. In contrast, the nuclear power system of this embodiment detects only the inlet gas temperature, inlet gas flow rate, outlet gas pressure, and neutron flux of the reactor core 11. The analysis unit 81 recreates the operating state of the reactor 112 in virtual space based on the inlet gas temperature, inlet gas flow rate, outlet gas pressure, and neutron flux, and outputs and monitors the core power distribution, core temperature distribution, and core outlet gas temperature distribution. This significantly reduces the number of detectors compared to monitoring and control of a pressurized water reactor, thereby reducing monitoring and control costs.

[0056] [Effects of this embodiment] The nuclear power system according to the first aspect comprises a core (reactor core) 11, a thermal conductor 13 that conducts heat generated by the nuclear reaction of nuclear fuel in the core 11 to the outside using a cooling medium, a reactivity control device 14 that has a plurality of control drums 51 arranged outside the core 11 and equipped with neutron absorption sections that absorb neutrons, a status detector 61 that detects the operating state of the reactor 112, and an analysis unit 81 that reproduces the operating state of the reactor 112 in a virtual space using a virtual model of the reactor 112 based on the detection results of the status detector 61.

[0057] According to the nuclear power system of the first aspect, in a micro reactor different from a light water reactor, the reactor 112 can be monitored by reproducing the operating state of the reactor 112 in a virtual space using a virtual model of the reactor 112 based on the operating state of the reactor 112 by the analysis unit 81. Therefore, the number of detectors can be reduced, thereby reducing the monitoring cost.

[0058] The nuclear system according to the second aspect is the nuclear system according to the first aspect, and further includes a state detector 61 having a temperature detector 71 for detecting the inlet gas temperature of the coolant in the thermal conductor 13, a flow rate detector 72 for detecting the inlet gas flow rate of the coolant in the thermal conductor 13, a pressure detector 73 for detecting the outlet gas pressure of the coolant in the thermal conductor 13, and a neutron flux detector 74 for detecting neutron flux in the core 11. This makes it possible to appropriately reproduce the operating state of the reactor 112 in a virtual space using a virtual model of the reactor 112.

[0059] The nuclear power system according to the third aspect is the nuclear power system according to the second aspect, and furthermore, the analysis unit 81 reproduces the operating state of the reactor 112 in a virtual space based on the inlet gas temperature, the inlet gas flow rate, the outlet gas pressure, and the neutron flux, and outputs the core power distribution, the core temperature distribution, and the core outlet gas temperature distribution. This makes it possible to appropriately monitor the operating state of the reactor 112.

[0060] The nuclear power system according to the fourth aspect is the nuclear power system according to the third aspect, and furthermore, the analysis unit 81 is multiplexed. By multiplexing the analysis unit 81, it is possible to ensure the data backup function of the analysis unit 81.

[0061] The nuclear power system according to the fifth aspect is the nuclear power system according to the second aspect, and further includes a control unit 82 that controls the reactivity control device 14 based on the operating state of the reactor 112 reproduced in the virtual space by the analysis unit 81. This makes it possible to appropriately control the operating state of the reactor 112. [Explanation of symbols]

[0062] 11 Core (nuclear reactor core) 12 Reflector 13 Thermal Conductors 14 Reactivity Control Device 31 Torso 32,33 wall 34 Torso 35,36 Support plate 37,38 Lid 41 Heat transfer tube 42 Inlet manifold 43 Outlet manifold 44 Inlet pipe 45 Outlet pipe 51 Control drum 52 Connecting part 53 Drive unit 57 Control Unit 60 Nuclear Systems 61 State Detector 62 Control device 63 Operation section 64 Display section 65 Storage section 71 Temperature detector 72 Flow detector 73 Pressure detector 74 Neutron Flux Detector 81 Analysis Department 82 Control Unit 100 Nuclear Power Systems 101 Reactor Unit 102 Refrigerant circulation path 103 Turbine 104 Compressor 105 Generator 106 Heat exchanger 107 Cooler 108,109 Connecting shaft 111 Reactor Vessel 112 Nuclear reactor 113 Heat transfer tube section

Claims

1. a reactor core; a thermal conductor that conducts heat generated by a nuclear reaction of nuclear fuel in the reactor core to the outside using a cooling medium; a reactivity control device having a plurality of control drums each provided with a neutron absorbing unit disposed outside the reactor core and absorbing neutrons; a status detector for detecting an operating status of the reactor; an analysis unit that reproduces an operating state of the reactor in a virtual space using a virtual model of the reactor based on the detection result of the state detector; A nuclear power system equipped with:

2. The state detector includes a temperature detector for detecting an inlet gas temperature of the cooling medium in the heat conductor, a flow rate detector for detecting an inlet gas flow rate of the cooling medium in the heat conductor, a pressure detector for detecting an outlet gas pressure of the cooling medium in the heat conductor, and a neutron flux detector for detecting neutron flux in the reactor core. The nuclear power system according to claim 1 .

3. the analysis unit reproduces the operating state of the reactor in a virtual space based on the inlet gas temperature, the inlet gas flow rate, the outlet gas pressure, and the neutron flux, and outputs a core power distribution, a core temperature distribution, and a core outlet gas temperature distribution. The nuclear power system according to claim 2 .

4. The analysis unit is multiplexed. The nuclear power system according to claim 1 .

5. a control unit that controls the reactivity control device based on the operating state of the reactor reproduced in the virtual space by the analysis unit; The nuclear power system according to claim 1 .

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