Arrangement of a high temperature gas cooled reactor module

Abstract

The application discloses a kind of high temperature gas cooled reactor module arrangement structures, including reactor plant, and nuclear auxiliary plant, electrical plant and main control room for reactor plant;Two independent, identical high temperature gas cooled reactor nuclear steam supply system modules are arranged in reactor plant.In the present scheme, the high temperature gas cooled reactor module containing two high temperature gas cooled reactor nuclear steam supply system modules is regarded as a standardized product, and can be assembled into a type unit according to market demand, under the premise that each high temperature gas cooled reactor nuclear steam supply system module has independent, identical inherent safety characteristics, so that multiple standardized modules can be independently operated and maintained, and the demand for long-term, continuous and stable supply of high temperature and high pressure industrial steam in various petrochemical parks is met.Furthermore, multiple high temperature gas cooled reactor modules can be flexibly combined to adapt to different load capacity, site conditions and construction scale.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear island design, in particular to a layout structure of a high-temperature gas cooled reactor module. BACKGROUND

[0002] The petrochemical industry is the second largest energy-consuming industry after the steel industry. Under the background of "carbon peak" and "carbon neutral", the oil and chemical industry, as a major consumer of coal and CO2 emitter, is facing an exceptionally severe challenge in its future development. The high-temperature gas cooled reactor nuclear steam supply system can provide high-quality process heat and industrial steam of various parameters, and has unique advantages in green and low-carbon heat energy supply. Its steam quantity, temperature and pressure are basically consistent with the parameters of the coal-fired boiler configured in a large petrochemical park, and it can be widely used in the oil and chemical industry, the steel and metallurgy industry, etc. to replace fossil energy. In the case of need, it can also implement combined heat and power supply, which can well meet the demand of large petrochemical parks for clean and efficient heat sources under the background of two carbons.

[0003] In nuclear energy utilization technology, it is often necessary to increase the single machine capacity or arrange multiple nuclear steam supply systems in combination to match market demand, achieve scale effect and reduce construction and operation costs. However, in the same type of technology, although the increase of single machine capacity can improve the economy to a certain extent, the nuclear safety guarantee capability may be weakened. Although the combination of multiple nuclear steam supply systems arranged in combination can take into account the economy and safety, each nuclear steam supply system is difficult to maintain independence in operation, maintenance or accident conditions, and it is difficult to avoid the mutual influence of other multiple nuclear steam supply systems arranged in combination. Although it can be widely used in power production, it cannot fully meet the demand of large petrochemical parks for long-term, continuous and stable supply of high-temperature and high-pressure industrial steam. SUMMARY

[0004] Therefore, the present application provides a layout structure of a high-temperature gas cooled reactor module. The high-temperature gas cooled reactor module containing two high-temperature gas cooled reactor nuclear steam supply system modules is taken as a standardized product, which can be assembled into a type of unit according to market demand. Under the premise of ensuring that each high-temperature gas cooled reactor nuclear steam supply system module has independent and identical inherent safety characteristics, multiple standardized modules can be independently operated and maintained, and can be alternately shut down for maintenance, which is suitable for the demand of various petrochemical parks for long-term, continuous and stable supply of high-temperature and high-pressure industrial steam. Moreover, multiple high-temperature gas cooled reactor modules can be flexibly combined, which is suitable for different load capacities, site conditions and construction scales.

[0005] To achieve the above-mentioned purpose, the present application provides the following technical scheme:

[0006] The layout structure of the high-temperature gas cooled reactor module comprises a reactor building, and a nuclear auxiliary building, an electrical building and a main control room matched with the reactor building.

[0007] Two independent, identical high-temperature gas-cooled reactor nuclear steam supply system modules are arranged in the reactor building.

[0008] Preferably, two one-loop compartments are arranged in the reactor building symmetrically along the center line of the reactor building, each of which contains one of the high-temperature gas-cooled reactor nuclear steam supply system modules.

[0009] Each of the one-loop compartments comprises a reactor pressure vessel compartment and a steam generator compartment.

[0010] Preferably, a compartment intermediate region is arranged in the reactor building between the two one-loop compartments, and a one-loop instrument room is arranged adjacent to each of the steam generator compartments, the compartment intermediate region and the one-loop instrument room being used to centrally arrange auxiliary and service facilities directly connected to and closely related to the two high-temperature gas-cooled reactor nuclear steam supply system modules.

[0011] Preferably, all facilities for containing one-loop coolant and any facilities, rooms and areas with the risk of releasing or leaking one-loop coolant are centrally arranged in the reactor building, and all facilities passing through the one-loop compartments, the compartment intermediate region and the one-loop instrument room are provided with electrical penetrations, mechanical penetrations or other sealing structures.

[0012] The radiation partition of the reactor building corridor is a conventional work area, the radiation partition of the nuclear auxiliary building is a conventional work area, and the radiation partition of the electrical building is a surveillance area.

[0013] Preferably, the one-loop compartment is a ventilated low-pressure containment.

[0014] Preferably, the outer wall of the reactor building is a single-sided or double-sided steel-concrete module structure, the inner wall is a single-sided, double-sided steel-concrete module structure or a reinforced concrete structure, and the one-loop compartment is a steel-concrete combined module structure.

[0015] Preferably, the nuclear auxiliary building is adjacent to the reactor building and located on one side of the steam generator compartment along the center line of the high-temperature gas-cooled reactor nuclear steam supply system module hot gas duct.

[0016] The electrical building is adjacent to the reactor building and located on one side of the reactor pressure vessel compartment along the center line of the high-temperature gas-cooled reactor nuclear steam supply system module hot gas duct.

[0017] Preferably, the main steam outlet of the steam generator compartment is led out along the center line of the one-loop compartment and out of the nuclear island through the nuclear auxiliary building.

[0018] The main feedwater inlet of the steam generator cabin is introduced through the nuclear auxiliary plant and connected to the steam generator along a primary circuit cabin center line.

[0019] Preferably, the main control room is arranged in the electrical plant along the direction of the electrical plant center line and distributed adjacent to the reactor plant.

[0020] Preferably, further comprising a spent fuel transport pipeline and a pipe gallery with shielding function;

[0021] The spent fuel transport pipeline is arranged in the pipe gallery and used for connecting a spent fuel storage facility and a fuel handling facility of the reactor plant.

[0022] From the above technical solutions, it can be seen that the arrangement structure of the high-temperature gas cooled reactor module provided by the application takes the high-temperature gas cooled reactor module containing two high-temperature gas cooled reactor nuclear steam supply system modules as a standardized product, which can be assembled into a type of unit according to market demand, ensures that each high-temperature gas cooled reactor nuclear steam supply system module has independent and same inherent safety characteristics, and makes multiple standardized modules be independently operated and maintained and alternately shut down for maintenance, which is suitable for the demand of long-term, continuous and stable supply of high-temperature and high-pressure industrial steam in various petrochemical parks; and the flexible combination of multiple high-temperature gas cooled reactor modules can be suitable for different load capacities, site conditions and construction scales. BRIEF DESCRIPTION OF DRAWINGS

[0023] In order to more clearly illustrate the technical solutions in the embodiments of the application or the prior art, the following will briefly introduce the drawings needed to be used in the embodiments or the prior art description. Obviously, the drawings in the following description only constitute some embodiments of the application, and for those skilled in the art, other drawings can also be obtained without creative labor based on these drawings.

[0024] Figure 1 The arrangement structure of the high-temperature gas cooled reactor module provided by the embodiment of the application is shown in the schematic view.

[0025] Among them, 1 is a reactor plant, 2 is a nuclear auxiliary plant, 3 is an electrical plant, 4 is a main control room, 5 is a primary circuit cabin, 6 is a reactor pressure vessel cabin, 7 is a steam generator cabin, 8 is a cabin intermediate area, 9 is a primary circuit instrument room, 10 is a main steam outlet, 11 is a new fuel transport pipeline, 12 is a pipe gallery, 13 is a reactor plant center line, and 14 is a primary circuit cabin center line. DETAILED DESCRIPTION

[0026] The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are only a part of the embodiments of the present invention, rather than all the embodiments. All other embodiments obtained by those of ordinary skill in the art based on the embodiments of the present invention without creative efforts shall fall within the protection scope of the present invention.

[0027] The layout structure of the high-temperature gas-cooled reactor module provided by the embodiment of the present invention is as Figure 1 shown, and includes a reactor building 1, and a nuclear auxiliary building 2, an electrical building 3 and a main control room 4 supporting the reactor building 1;

[0028] There are two independent and identical high-temperature gas-cooled reactor nuclear steam supply system modules arranged in the reactor building 1.

[0029] It should be noted that the high-temperature gas-cooled reactor module of this solution takes the reactor building 1 containing two high-temperature gas-cooled reactor nuclear steam supply system modules as the core, and is equipped with a separate nuclear auxiliary building 2, an electrical building 3 and a main control room 4, making it a standardized product that can be arbitrarily assembled into a certain type of unit according to market demand. On the premise of ensuring that each nuclear steam supply system module has independent and identical inherent safety characteristics, multiple standardized modules can be independently operated and maintained, and can be shut down for maintenance in turn, meeting the needs of various petrochemical industrial parks for long-term, continuous and stable supply of high-temperature and high-pressure industrial steam; by flexibly combining multiple high-temperature gas-cooled reactor modules, it can be applicable to different load capacities, site conditions and construction scales.

[0030] As can be seen from the above technical solutions, the layout structure of the high-temperature gas-cooled reactor module provided by the embodiment of the present invention takes the high-temperature gas-cooled reactor module containing two high-temperature gas-cooled reactor nuclear steam supply system modules as a standardized product, which can be arbitrarily assembled into a certain type of unit according to market demand. On the premise of ensuring that each high-temperature gas-cooled reactor nuclear steam supply system module has independent and identical inherent safety characteristics, multiple standardized modules can be independently operated and maintained, and can be shut down for maintenance in turn, meeting the needs of various petrochemical industrial parks for long-term, continuous and stable supply of high-temperature and high-pressure industrial steam; by flexibly combining multiple high-temperature gas-cooled reactor modules, it can be applicable to different load capacities, site conditions and construction scales.

[0031] Furthermore, as Figure 1 shown, there are two primary loop compartments 5 symmetrically arranged along the center line 13 of the reactor building 1 in the reactor building 1, and each primary loop compartment 5 contains a high-temperature gas-cooled reactor nuclear steam supply system module;

[0032] Each primary loop compartment 5 includes a reactor pressure vessel compartment 6 and a steam generator compartment 7. This design not only helps maintain the operating environment of critical facilities in each high-temperature gas-cooled reactor nuclear steam supply system module, but also helps ensure the safety characteristics of the high-temperature gas-cooled reactor nuclear steam supply system module.

[0033] Furthermore, such as Figure 1 As shown, within the reactor building 1, an intermediate zone 8 is arranged between the two primary loop compartments 5, and a primary loop instrument room 9 is arranged adjacent to each steam generator compartment 7. The intermediate zone 8 and the primary loop instrument room 9 are used to centrally house auxiliary and service facilities that are directly connected to and closely related to the nuclear steam supply system modules of the two high-temperature gas-cooled reactors, so as to realize the rational use of the intermediate and surrounding areas of the two primary loop compartments 5 and contribute to a compact and intensive layout. In addition, the auxiliary and service facilities arranged in the intermediate zone 8, from bottom to top, include fuel loading and unloading facilities, vaporizer emergency discharge facilities, helium purification and helium auxiliary facilities, primary loop pressure relief facilities, absorber ball facilities, negative pressure exhaust facilities, and fuel lifting facilities; the primary loop instrument room 9 houses primary loop instruments and monitoring facilities of different sequences that are directly connected to the nuclear steam supply system modules of the two high-temperature gas-cooled reactors.

[0034] In this scheme, reactor building 1 is centrally located with facilities, rooms and areas for containing the primary coolant, as well as any facilities, rooms and areas where there is a risk of release or leakage of the primary coolant, so as to control the impact range of the radioactive area to the maximum extent. All facilities passing through the primary coolant compartment 5, the intermediate compartment area 8 and the primary coolant instrument room 9 are equipped with electrical penetrations, mechanical penetrations or other sealed structures to ensure that radioactive air does not leak into the surrounding rooms, corridors and areas, and does not affect the establishment of negative pressure in the primary coolant compartment 5, the intermediate compartment area 8 and the primary coolant instrument room 9.

[0035] The radiation zone of the reactor building 1 corridor is a conventional working area (green zone), the radiation zone of the nuclear auxiliary building 2 is a conventional working area (green zone), and the radiation zone of the electrical building 3 is a monitored area (white zone). This can effectively control the range of influence of the radioactive area, facilitate centralized inspection and personnel passage, and help the independent operation and maintenance of multiple standardized modules and the rotation of reactor shutdown for maintenance.

[0036] Specifically, primary loop compartment 5 is a ventilated, low-pressure containment. In other words, each high-temperature gas-cooled reactor nuclear steam supply system module inside reactor building 1 is surrounded by an independent ventilated, low-pressure containment, which can withstand the internal pressure of an accident and contain radioactive materials, ensuring that no large-scale radioactive release will occur under any accident conditions.

[0037] In order to further optimize the above technical solutions, the outer wall of the reactor building 1 is a single-sided steel concrete module structure or a double-sided steel concrete module structure, the inner wall of the reactor building 1 is a single-sided steel concrete module structure, a double-sided steel concrete module structure or a reinforced concrete structure; and the primary loop cabin 5 is a steel concrete combined module structure. The design can ensure the structural rigidity of the reactor building 1 and the primary loop cabin 5. Of course, the steel plate module can be used as a concrete pouring formwork, thereby reducing the construction process and accelerating the engineering progress.

[0038] Further, in order to realize a reasonable, feasible, and as short as possible high-energy pipeline and convenient electrical outlet, correspondingly, as shown in Figure 1 , the nuclear auxiliary building 2 is adjacent to the reactor building 1 and is located on one side of the steam generator cabin 7 along the center line direction of the high-temperature gas cooled reactor nuclear steam supply system module hot gas guide pipe;

[0039] The electrical building 3 is adjacent to the reactor building 1 and is located on one side of the reactor pressure vessel cabin 6 along the center line direction of the high-temperature gas cooled reactor nuclear steam supply system module hot gas guide pipe.

[0040] Further, the main steam outlet 10 of the steam generator cabin 7 is led out along the primary loop cabin center line 14 and out of the nuclear island through the nuclear auxiliary building 2, so that the main steam outlet 10 is short and convenient and the planning is reasonable.

[0041] The main feed water inlet of the steam generator cabin 7 is introduced through the nuclear auxiliary building 2 and connected to the steam generator along the primary loop cabin center line 14, so that the main feed water inlet is also short and convenient and the planning is reasonable.

[0042] In the present scheme, as shown in Figure 1 , the main control room 4 is arranged in the electrical building 3 along the electrical building center line and is adjacent to the reactor building 1, so that the cable is conveniently and neatly in and out.

[0043] Specifically, the arrangement structure of the high-temperature gas cooled reactor module provided by the embodiment of the present application, as shown in Figure 1 , further comprises a spent fuel transport pipeline and a pipe gallery 12 with shielding function;

[0044] The spent fuel transport pipeline is arranged in the pipe gallery 12 and is used to connect the spent fuel storage facility and the fuel loading and unloading facility of the reactor building 1. That is, the spent fuel transport pipeline is arranged in the pipe gallery 12 (which can also be a pipe well) with shielding function, which greatly reduces the irradiation dose of the surrounding area caused by the transport of the spent fuel element.

[0045] The present scheme will be further described in combination with specific embodiments as follows:

[0046] The arrangement structure of the high-temperature gas cooled reactor module provided by the present application is further introduced as follows:

[0047] 1. The high temperature gas cooled reactor module is centered on a reactor building containing two high temperature gas cooled reactor nuclear steam supply system modules, and is matched with a nuclear auxiliary building, an electrical building and a main control room, and forms an independent rectangular module; in order to realize reasonable, feasible and as short as possible high-energy pipelines and convenient electrical outlet, the nuclear auxiliary building is located on the side of the evaporator cabin of the reactor building along the axis direction of the nuclear steam supply module hot gas duct, and the electrical building is located on the side of the reactor cabin along the axis direction of the nuclear steam supply module hot gas duct;

[0048] 2. Two primary loop cabins are symmetrically arranged along the center line in the reactor building, the reactor pressure vessel and the steam generator are respectively located in the reactor pressure vessel cabin and the steam generator cabin of the primary loop cabin, the nuclear steam supply system modules are symmetrically arranged to realize the reasonable use of the central and peripheral areas of the cabin, and the auxiliary and service facilities directly connected with and closely related to the two sets of nuclear steam supply system modules are compactly and intensively arranged, from bottom to top, the fuel loading and unloading facilities, the evaporator accident discharge facilities, the helium purification and helium auxiliary facilities, the primary loop pressure relief facilities, the absorber ball facilities, the primary loop instrument and monitoring facilities, the negative pressure exhaust facility and the fuel lifting facility are arranged; the top layer of the reactor building is a maintenance hall, an equipment transportation gate is opened towards the outside, and the key facilities such as the main helium fan and the steam generator in the high temperature gas cooled reactor nuclear steam supply system module can enter (exit) the reactor building through the equipment transportation gate during construction and in service;

[0049] 3. Each nuclear steam supply system module is surrounded by an independent ventilated low-pressure containment (i.e. a primary loop cabin); in view of the defects of pipeline crossing complexity, air flow organization and atmosphere isolation complexity existing in the dispersed arrangement of the containment body in the same type of technology, all other containment primary loop coolants and any facilities, rooms and areas that may release or leak primary loop coolants are arranged in the reactor building, forming a containment body that can withstand the internal pressure of an accident and realize the containment of radioactive substances, and the influence range of the radioactive area is maximized; the negative pressure exhaust facility is arranged just above the containment body, so as to ensure that there will be no large-scale radioactive release under any accident condition; all facilities passing through the containment body adopt electrical penetrations, mechanical penetrations or other sealing structures, so as to realize that the radiation partition of the corridor of the reactor building is a conventional working area, the radiation partition of the nuclear auxiliary building is a conventional working area, and the radiation partition of the electrical building is a supervision area, which is helpful for independent operation and maintenance and turn-to-turn maintenance of multiple standardized modules;

[0050] 4、The two primary loop cabins in the reactor building are steel-concrete composite module structures; the outer wall of the reactor building is a single-sided (HSC) or double-sided (SC) steel-concrete modular structure, and the inner wall of the reactor building is a SC module structure or a reinforced concrete structure (RC) or a single-sided steel-concrete (HSC) module structure; the steel plate module can be used as a concrete pouring formwork, reducing the construction process and accelerating the project progress;

[0051] 5、The main steam outlet line is led out along the center line of the primary loop cabin, passes through the nuclear auxiliary building, and exits the nuclear island; the main feedwater inlet line passes through the nuclear auxiliary building and connects the steam generator along the center line of the primary loop cabin;

[0052] 6、The overall electrical building adopts the arrangement form of "cable interlayer-equipment layer-cable interlayer", different redundant channel cables and corresponding safety level equipment are arranged in the same area and are communicated with the corresponding safety level cable shaft, and then are led out to the cable corridor area in the reactor building, different safety channels are arranged in layers, and the entities between different redundant channels are isolated;

[0053] 7、The main control room is arranged along the center line in the electrical building and close to the reactor building; the main control room is located directly above the main control equipment room and the electrical equipment room, so that the cables in the module can be neatly in and out;

[0054] 8、The new fuel supply facility is connected with the fuel handling facility in the reactor building through a new fuel ball tube (new fuel pipeline), and the new fuel elements are transported to the loading temporary storage device of the fuel handling system in a mechanical lifting or pneumatic conveying manner through the new fuel ball tube; the spent fuel storage facility is connected with the fuel handling facility in the reactor building through a spent fuel ball tube (spent fuel pipeline); the spent fuel ball tube is independently arranged in a pipe gallery or pipe well with shielding function, which greatly reduces the irradiation dose of the spent fuel element transportation to the surrounding area, eliminates the radioactive influence of the single module by the multi-module spent fuel element transportation line; the spent fuel elements are transported to the spent fuel storage room through the spent fuel ball tube in a mechanical lifting or pneumatic conveying manner.

[0055] The beneficial effects of the present application are:

[0056] 1、The present application takes a reactor building containing two high-temperature gas-cooled reactor nuclear steam supply system modules as the core, matches a separate nuclear auxiliary building, an electrical building and a main control room for the reactor building, and forms an independent rectangular module; the module is taken as a standardized product, and a type of unit can be assembled at will according to market demand; under the premise that each nuclear steam supply system module has independent and same inherent safety characteristics, multiple standardized modules can be independently operated and maintained and are taken turns to shut down for maintenance, which is suitable for the needs of long-term, continuous and stable supply of high-temperature and high-pressure industrial steam in various petrochemical parks; multiple high-temperature gas-cooled reactor modules can be flexibly combined, which is suitable for different load capacities, site conditions and construction scales;

[0057] 2. Each nuclear steam supply system module is surrounded by an independent vented low pressure containment (i.e. primary loop cabin), other facilities, rooms and areas containing primary loop coolant and any possible release, leakage of primary loop coolant are all arranged in close proximity, centralized in the reactor building, forming a containment body, which can withstand the internal pressure of the accident and achieve the containment of radioactive substances, the negative pressure exhaust facility is arranged in close proximity above the containment body, to ensure that there will be no large-scale radioactive release under any accident conditions; all facilities passing through the containment body use electrical penetrations, mechanical penetrations or other sealing structures to facilitate the radiation zoning of the reactor building corridor as a conventional work area, the radiation zoning of the nuclear auxiliary building as a conventional work area, and the radiation zoning of the electrical building as a supervision area, which helps the independent operation and maintenance of multiple standardized modules and the rotation of shutdown maintenance;

[0058] 3. The two primary loop cabins in the reactor building are steel-concrete composite modules; the outer wall of the reactor building is a single-sided (HSC) or double-sided (SC) steel-concrete modular structure, the inner wall of the reactor building is an SC module structure or a reinforced concrete structure (RC) or a single-sided steel-concrete (HSC) module structure; steel plate modules can be used as concrete pouring forms to reduce construction procedures and speed up project progress;

[0059] 4. The reactor building is compactly arranged, and the auxiliary and service facilities closely related to the two nuclear steam supply system modules are centrally arranged in the area between and around the two primary loop cabins; the equipment transfer path is reasonable, including during service and construction, the steam generator can be accessed (exited) from the reactor building through the roof of the reactor building; the electrical and instrument control cables, main steam and main water supply pipelines, and outgoing and incoming lines for new fuel and spent fuel transportation are convenient and clean, and the path planning is reasonable, feasible and short.

[0060] The various embodiments in the specification are described in a progressive manner, and each embodiment focuses on the differences from other embodiments. The same or similar parts between the various embodiments can be referred to each other.

[0061] The above description of the disclosed embodiments enables a person skilled in the art to implement or use the present application. Various modifications to these embodiments will be apparent to those skilled in the art, and the general principles defined herein can be implemented in other embodiments without departing from the spirit or scope of the present application. Therefore, the present application will not be limited to these embodiments shown herein, but will conform to the widest scope consistent with the principles and novel features disclosed herein.

Claims

1. An arrangement structure for a high-temperature gas-cooled reactor module, characterized in that, It includes a reactor building (1), and a nuclear auxiliary building (2), an electrical building (3) and a main control room (4) that are associated with the reactor building (1). The reactor building (1) contains two independent, identical high-temperature gas-cooled reactor nuclear steam supply system modules; Two primary loop compartments (5) are symmetrically arranged along the center line (13) of the reactor building (1), and each primary loop compartment (5) contains a nuclear steam supply system module of the high-temperature gas-cooled reactor. Each of the primary loop compartments (5) includes a reactor pressure vessel compartment (6) and a steam generator compartment (7). The reactor building (1) contains a central compartment (8) between the two primary loop compartments (5) and a primary loop instrument room (9) adjacent to each of the steam generator compartments (7). The central compartment (8) and the primary loop instrument room (9) are used to centrally arrange auxiliary and service facilities that are directly connected to and closely related to the two high-temperature gas-cooled reactor nuclear steam supply system modules. The auxiliary and service facilities arranged in the central compartment (8) from bottom to top include fuel loading and unloading facilities, evaporator accident emission facilities, helium purification and helium auxiliary facilities, primary loop pressure relief facilities, absorption ball facilities, negative pressure exhaust facilities, and fuel lifting facilities. The auxiliary and service facilities arranged in the primary loop instrument room (9) include primary loop instruments and monitoring facilities. The reactor building (1) contains facilities and areas for containing the primary coolant and any facilities and areas where there is a risk of leakage of the primary coolant; all facilities passing through the primary coolant compartment (5), the intermediate area of ​​the compartment (8), and the primary instrument room (9) are equipped with electrical and mechanical penetrations. The radiation zone of the reactor building (1) corridor is a conventional work area, the radiation zone of the nuclear auxiliary building (2) is a conventional work area, and the radiation zone of the electrical building (3) is a monitoring area.

2. The arrangement structure of the high-temperature gas-cooled reactor module according to claim 1, characterized in that, The primary loop compartment (5) is a ventilated, low-pressure containment.

3. The arrangement structure of the high-temperature gas-cooled reactor module according to claim 1, characterized in that, The outer wall of the reactor building (1) is a single-sided steel plate concrete module structure or a double-sided steel plate concrete module structure, and the inner wall of the reactor building (1) is a single-sided steel plate concrete module structure, a double-sided steel plate concrete module structure or a reinforced concrete structure; the primary loop compartment (5) is a steel plate concrete composite module structure.

4. The arrangement structure of the high-temperature gas-cooled reactor module according to claim 1, characterized in that, The nuclear auxiliary building (2) is adjacent to the reactor building (1), and the nuclear auxiliary building (2) is located on one side of the steam generator compartment (7) along the center line direction of the hot gas duct of the high temperature gas-cooled reactor nuclear steam supply system module. The electrical building (3) is adjacent to the reactor building (1), and the electrical building (3) is located on one side of the reactor pressure vessel compartment (6) along the center line direction of the hot gas duct of the high temperature gas-cooled reactor nuclear steam supply system module.

5. The arrangement structure of the high-temperature gas-cooled reactor module according to claim 4, characterized in that, The main steam outlet line (10) of the steam generator compartment (7) is led out along the center line (14) of the primary loop compartment and exits the nuclear island through the nuclear auxiliary building (2); The main feedwater inlet of the steam generator compartment (7) is introduced through the nuclear auxiliary building (2) and connected to the steam generator along the center line (14) of the primary loop compartment.

6. The arrangement structure of the high-temperature gas-cooled reactor module according to claim 4, characterized in that, The main control room (4) is located in the electrical plant (3) along the center line of the electrical plant and is adjacent to the reactor plant (1).

7. The arrangement structure of the high-temperature gas-cooled reactor module according to claim 1, characterized in that, It also includes spent fuel transport pipelines and shielded utility tunnels (12). The spent fuel transport pipeline is arranged in the pipe gallery (12) and is used to connect the spent fuel storage facility with the fuel loading and unloading facility of the reactor building (1).

Images