Fixed related assembly of nuclear reactor core

Abstract

A fixed related assembly of a nuclear reactor core, comprising functional rods (1) for being inserted into guide tubes of a fuel assembly (3) to achieve different functions, and a pressing system (2) for fixing and connecting the functional rods (1). The pressing system (2) comprises a central cylinder (21) having an inner cavity, and a supporting plate (22); the supporting plate (22) is fixedly connected to the central cylinder (21); the inner cavity of the central cylinder (21) comprises a first cavity (211). The pressing system (2) further comprises a pressing structure (23); the pressing structure (23) comprises a pressing rod (231), a pressing spring (232), and a spring seat (233); the pressing spring (232) fills the first cavity (211); one end of the spring seat (233) penetrates into the first cavity (211) and abuts against the lower end of the pressing spring (232), and the other end of the spring seat (233) is used for pressing against an upper tube seat of the fuel assembly (3); the pressing rod (231) is fixedly connected to the central cylinder (21), and is located at the side of the supporting plate (22) away from the spring seat (233); the pressing rod (231) is used for abutting against the side of a reactor core upper plate (4) of the nuclear reactor core close to the fuel assembly (3), so as to prevent a related assembly from axially moving.

Description

Stationary components related to nuclear reactor cores Technical Field

[0001] The present invention relates to the technical field of nuclear reactors, and more particularly to a fixed component related to a nuclear reactor core. Background Art

[0002] Core-related components can be divided into control rod assemblies and fixed-type related components. The fixed-type related components can be divided into primary neutron source assemblies, secondary neutron source assemblies, and choke plug assemblies according to their functions. They consist of a clamping system and functional rods (which can be divided into primary neutron source rods, secondary neutron source rods, choke plug rods, etc.).

[0003] The structure of the fixed related component clamping system of the prior art is shown in Figure 1, and is composed of a support plate A, a guide cylinder B, a clamping spring group C, and a clamping rod D. The support plate A of the clamping system is a square plate structure with a water flow hole and a positioning hole for installing related rods in the middle; the guide cylinder B is a cylindrical structure with two symmetrical guide grooves on the tube wall of the guide cylinder B, which cooperate with the clamping rod D through a pin E to limit the compression stroke of the spring; the clamping rod D is a conjugate symmetrical structure, consisting of a circular ring structure with a central opening and conjugate rods on both sides; the clamping spring group C is composed of a pair of double-layer springs, which are sleeved on the outside of the guide cylinder B, with the upper end limited by the clamping rod D and the lower end sitting on the support plate A; the lower part of the guide cylinder B passes through the center hole of the support plate A and is welded to the support plate A, and the upper part is sleeved with the clamping rod D, and the axial stroke of the clamping rod D is limited to the range of the guide cylinder pin groove through the pin E.

[0004] When operating within a nuclear reactor, the existing compression system maintains contact between the bottom of the compression system and the upper tube seat of the fuel assembly, and the top of the compression system maintains contact with the upper core plate via the compression rod D. As the fuel assembly grows under irradiation, the gap between the upper tube seat and the upper core plate gradually decreases. The compression rod D moves downward relative to the guide tube B, compressing the compression spring assembly C, which continuously applies a downward pressure to the support plate. To ensure that the relevant components do not jump under the action of hydraulic lifting force during operation within the reactor, the compression force must meet the following conditions:

[0005] Compacting force + gravity of related components > hydraulic lifting force

[0006] In the above formula, the hydraulic lifting force on the relevant components is generally much greater than the gravity. Therefore, the compression spring needs to be greater than the hydraulic lifting force minus the gravity, and the required compression force is relatively large. Summary of the Invention

[0007] The technical problem to be solved by the present invention is to provide a fixed related component of a nuclear reactor core in response to the above-mentioned defects of the prior art.

[0008] The technical solution adopted by the present invention to solve the technical problem is: a fixed-type related component of a nuclear reactor core, including functional rods for inserting into fuel assembly guide tubes to achieve different functions and a clamping system for fixing and connecting the functional rods, the clamping system including a central tube with an inner cavity and a support plate, the support plate being fixedly connected to the central tube;

[0009] The inner cavity of the central tube includes a first cavity, and the pressing system further includes a pressing structure, and the pressing structure includes a pressing rod, a pressing spring and a spring seat;

[0010] The compression spring is filled in the first cavity, one end of the spring seat is passed into the first cavity and abuts against the lower end of the compression spring, and the other end of the spring seat is used to press the upper tube seat of the fuel assembly. The compression rod is fixedly connected to the center tube and is located on the side of the support plate away from the spring seat. The compression rod is used to abut against the side of the upper core plate of the nuclear reactor core close to the fuel assembly to prevent axial movement of the relevant components.

[0011] In some embodiments, a stopper is provided in the first cavity, and the stopper abuts against the upper end of the compression spring.

[0012] In some embodiments, when the fuel assembly is irradiated and grown during operation in a reactor, and the gap between the fuel assembly and the upper plate of the core is reduced, the spring seat moves axially along the first cavity toward the compression rod to compress the compression spring.

[0013] In some embodiments, a limiting protrusion is provided at one end of the spring seat close to the first cavity, and a limiting member is also provided on the cavity wall of the first cavity. The limiting protrusion abuts against the limiting member to prevent the spring seat from escaping from the first cavity.

[0014] In some embodiments, the inner cavity of the central tube further includes a second cavity connected to the first cavity, and the second cavity is farther away from the support plate than the first cavity; wherein a hanging groove is provided on the cavity wall of the second cavity.

[0015] In some embodiments, the central tube includes a first tube body and a second tube body, and the support plate is fixedly connected to the second tube body; the inner cavity of the first tube body includes a first sub-cavity, and the inner cavity of the second tube body includes a second sub-cavity. When the first tube body and the second tube body are connected and combined into the central tube, the first sub-cavity and the second sub-cavity are connected to form the first cavity.

[0016] In some embodiments, the second cylinder includes at least two sub-cylinders, each of which has a cavity running through its axial direction. When multiple sub-cylinders are connected and combined to form the second cylinder, the cavities of the multiple sub-cylinders are connected to form the second sub-cavity.

[0017] In some embodiments, the first cylinder and the second cylinder are connected by girth welding.

[0018] In some embodiments, the sub-cylinders are connected by girth welding.

[0019] In some embodiments, the support plate is provided with through holes for coolant to flow through; and / or;

[0020] The support plate is also provided with a mounting hole for the functional rod to pass through.

[0021] The implementation of the present invention has the following beneficial effects: the fixed related components of the nuclear reactor core using the present invention can reduce the compression force borne by the compression system, extend the service life of the compression system, and at the same time reduce the pressure drop of the coolant when flowing through the component, improve the cooling effect of the coolant, and ensure the stable operation of the nuclear reactor. BRIEF DESCRIPTION OF THE DRAWINGS

[0022] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:

[0023] FIG1 is a schematic diagram of a fixed-type related component compression system in the prior art;

[0024] FIG2 is a schematic diagram of fixed components related to a nuclear reactor core according to an embodiment of the present invention;

[0025] FIG3 is a schematic diagram of a compression system according to an embodiment of the present invention;

[0026] FIG4 is a cross-sectional view of a compression system according to an embodiment of the present invention;

[0027] FIG5 is a schematic diagram of the core upper plate, fixed related components of the nuclear reactor core, and the fuel assembly during in-core operation according to an embodiment of the present invention;

[0028] 6 is a cross-sectional view of the center tube of the clamping system in sections above the clamping rod according to an embodiment of the present invention;

[0029] FIG7 is a cross-sectional view of a center tube of a compaction system divided into multiple sections according to an embodiment of the present invention. DETAILED DESCRIPTION

[0030] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific embodiments of the present invention are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the directions or positional relationships indicated by "front", "back", "up", "down", "left", "right", "longitudinal", "horizontal", "vertical", "horizontal", "top", "bottom", "inside", "outside", "head", "tail", etc. are based on the directions or positional relationships shown in the accompanying drawings, are constructed and operated in specific directions, and are only for the convenience of describing the technical solution, and do not indicate that the devices or components referred to must have specific directions, and therefore should not be understood as limiting the present invention.

[0031] It should also be noted that, unless otherwise clearly specified and limited, terms such as "installed", "connected", "connected", "fixed", and "set" should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integrated connection; it can be a mechanical connection or an electrical connection; it can be directly connected or indirectly connected through an intermediate medium, and it can be the internal connection of two elements or the interaction relationship between two elements. When an element is referred to as being "on" or "under" another element, the element can be "directly" or "indirectly" located on the other element, or there may be one or more intervening elements. The terms "first", "second", "third", etc. are only for the convenience of describing the present technical solution, and cannot be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, the features defined as "first", "second", "third", etc. may explicitly or implicitly include one or more of such features. For those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood according to the specific circumstances.

[0032] In the following description, specific details such as particular system structures and techniques are provided for purposes of illustration, not limitation, to facilitate a thorough understanding of the embodiments of the present invention. However, it will be apparent to those skilled in the art that the present invention may be practiced in other embodiments without these specific details. In other cases, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present invention with unnecessary detail.

[0033] Figures 2 through 7 illustrate fixed components of a nuclear reactor core according to some embodiments of the present invention. These components include a functional rod 1 and a clamping system 2. The functional rod 1 is inserted into a guide tube of a fuel assembly 3 to achieve various functions, while the clamping system 2 secures and connects the functional rod 1.

[0034] Therefore, the fixed related components of the nuclear reactor core of the present invention can reduce the compression force borne by the compression system 2, extend the service life of the compression system 2, and at the same time reduce the pressure drop when the coolant flows through this component, improve the cooling effect of the coolant, and ensure the stable operation of the nuclear reactor.

[0035] The clamping system 2 includes a central tube 21 with an inner cavity, a support plate 22 and a clamping structure 23. As shown in Figures 2 to 4, the support plate 22 is fixedly connected to the central tube 21. It should be noted that the fixed connection between the two described in the embodiments of the present application includes: the two are integrally formed; or the two are connected by welding, riveting, welding and interference fit, and the two fixed connections remain relatively stationary. The fixed connection mentioned below is also explained in this way, and all include integral molding, which will not be repeated. In some embodiments, the support plate 22 and the central tube 21 can also be detachably connected together, which is convenient for disassembly and replacement, and is not limited here.

[0036] The inner cavity of the central tube 21 includes a first cavity 211, and the support plate 22 is a square plate-shaped structure. The support plate 22 is provided with a through hole 221 for the coolant to flow through; and / or, the support plate 22 is provided with a mounting hole 222 for the functional rod 1 to pass through. For example, in some embodiments, the support plate 22 may be provided with a through hole 221 for the coolant to flow through, so that the coolant can cool the nuclear reactor and maintain the stable operation of the nuclear reactor. For another example, in some embodiments, the support plate 22 may also be provided with a mounting hole 222 for the functional rod 1 to pass through. After passing through the mounting hole 222, the functional rod 1 is installed and fixed in the mounting hole 222, so that the clamping system 2 fixes and connects the functional rod 1.

[0037] The compression structure 23 includes a compression rod 231, a compression spring 232, and a spring seat 233. The compression spring 232 is installed in the first cavity 211. One end of the spring seat 233 extends into the first cavity 211 and abuts against the lower end of the compression spring 232. The other end of the spring seat 233 is used to press against the upper tube seat 31 of the fuel assembly 3. Specifically, please refer to Figure 3. The compression spring 232 penetrates into the inner cavity and is slidably installed in the first cavity 211. In order to prevent the compression spring 232 from continuing to move upward along the inner cavity and pass through the interior of the center tube 21, there is a stopper 2111 in the first cavity 211. When the compression spring 232 penetrates into the first cavity 211, the upper end of the compression spring 232 abuts against the stopper 2111. The stopper 2111 prevents the compression spring 232 from continuing to move upward along the inner cavity of the center tube 21, so that the compression spring 232 is limited to the first cavity 211 for expansion and contraction, preventing the compression spring 232 from escaping from the first cavity 211.

[0038] Further, referring to Figure 3, a limiting protrusion 2331 is provided at one end of the spring seat 233 close to the first cavity 211, and a limiting member 2112 is further provided on the cavity wall of the first cavity 211. The limiting member 2112 is arranged at the lower end of the first cavity 211. When the spring seat 233 is inserted into the first cavity 211, the limiting protrusion 2331 abuts against the limiting member 2112 to prevent the spring seat 233 from escaping from the first cavity 211.

[0039] The clamping rod 231 is fixedly connected to the center tube 21 and is located on the side of the support plate 22 away from the spring seat 233. The side of the clamping rod 231 away from the support plate 22 is used to abut against the side of the core upper plate 4 of the nuclear reactor core close to the fuel assembly 3. In some embodiments, the clamping rod 231 is integrally formed with the center tube 21. Of course, in some embodiments, the clamping rod 231 and the center tube 21 can also be detachably connected together. For example, as shown in Figures 3 and 4, the clamping rod 231 is in the shape of an elongated strip and is axially symmetrical with the center tube 21.

[0040] When the fixed-type related components are installed in the nuclear reactor core, the upper end of the clamping rod 231 abuts against the core upper plate 4, and the lower end of the spring seat 233 abuts against the upper tube seat 31 of the fuel assembly 3. Specifically, as shown in Figure 5, the core upper plate 4, the clamping system 2, and the fuel assembly 3 are installed axially from top to bottom, with the functional rod 1 inserted into the guide tube of the fuel assembly 3. The clamping system 2 is used to fix the functional rod 1 so that it remains at a fixed axial height. During assembly operation, the side of the spring seat 233 away from the clamping spring 232 presses against the upper tube seat 31 of the fuel assembly 3, and the side of the clamping rod 231 away from the support plate 22 abuts against the core upper plate 4, ensuring that the clamping system 2 is always fixed between the upper tube seat 31 of the fuel assembly 3 and the core upper plate 4.

[0041] When the nuclear reactor is in operation, the fuel assembly 3 grows with irradiation, causing the gap between the fuel assembly 3 and the core upper plate 4 to decrease. At this time, since the lower end of the spring seat 233 presses against the upper surface of the upper tube seat 31 of the fuel assembly 3, the spring seat 233 will move along the axial direction of the first cavity 211 toward the direction close to the clamping rod 231, thereby compressing the clamping spring 232 so that its clamping system 2 provides an upward clamping force.

[0042] During operation of the fuel assembly 3, the fixed components of this application must remain fixed under the hydraulic lifting force of the core coolant and must not experience axial runout. Since the compression force provided by the compression spring 232 in this application is upward, the following adjustments must be met to ensure that the components remain fixed and do not experience axial runout under the hydraulic lifting force of the core coolant:

[0043] Hydraulic lifting force + spring compression force > related components' self-weight

[0044] Furthermore, since hydraulic lifting forces are generally much greater than the self-weight of the relevant components, the fixed-type relevant components in this application only need to ensure that the compression rod 231 maintains contact with the core upper plate 4 under cold operating conditions. In other words, the spring compression force generated by the compression spring 232 within the compression system 2 is greater than the self-weight of the relevant components. Compared with the prior art, the compression force required by the fixed-type relevant components of the nuclear reactor core in this application is significantly reduced. In this way, on the one hand, the stress on the compression spring 232 can be reduced, which is conducive to effectively delaying the aging of the compression spring 232, extending the service life of the compression spring 232, and thus extending the service life of the fixed related components of the nuclear reactor core; on the other hand, the size of the compression spring 232 can be reduced, and there is no need to set a double-layer spring on the outside of the central tube 21, thereby reducing the plate solid area of ​​the support plate 22 used to support the double-layer spring on the outside of the central tube 21, which can be used to increase the flow field area on the support plate 22 for the circulation of coolant, thereby reducing the pressure loss caused by the resistance of the support plate 22 when the coolant flows through the compression system 2.

[0045] In some embodiments, the center tube 21 further includes a second cavity 212, which is formed in an inner cavity above the center tube 21 and communicates with the first cavity 211. The second cavity 212 is further away from the support plate 22 than the first cavity 211. In addition, a lifting groove 2121 is provided on the wall of the second cavity 212. The lifting groove 2121 can cooperate with a lifting tool so that the lifting tool can lift and move fixed related components. In some embodiments, the size of the lifting groove 2121 can be designed according to the lifting tool used to lift the control rods of a nuclear reactor, that is, the lifting groove 2121 can cooperate with the lifting tool used to lift the control rods of a nuclear reactor, so that the device and the control rods can share the lifting tool.

[0046] It should be noted that in the prior art (as shown in the embodiment of FIG1 ), since the spring assembly constantly applies a downward compressive force to the support plate, the sum of this compressive force and the weight of the associated components must be greater than the hydraulic lift force to prevent the associated components from jumping during hydraulic lift during in-stack operation. However, the hydraulic lift force applied to the associated components is generally much greater than the gravity. To prevent axial movement of the associated components, a relatively high compressive force is required. Therefore, in the prior art, a double-layer spring is installed on the outside of the center tube to increase the compressive force. Furthermore, the use of a double-layer spring on the outside of the center tube in the prior art results in a smaller diameter within the center tube, making it difficult to design a lifting slot within the tube. Therefore, lifting is required only through the external clamping rods, and the control rods cannot be lifted using the same lifting tools. However, as previously described, in the embodiments of the present application, a relatively low clamping force can prevent axial movement of the fixed associated components, reducing the size of the clamping spring 232 and eliminating the need for a spring on the outside of the center tube 21. In the embodiment of the present application, there is no need to provide a spring on the outside of the center tube 21. Thus, the outer diameter of the center tube 21 can be increased to be consistent with the outer diameter of the control rod center tube 21. At this time, the inner diameter of the center tube 21 of the clamping system 2 can also be increased accordingly. This allows the inner cavity of the center tube 21 of the clamping system 2 to be designed as a second cavity 212 of the same size as the control rod-related components, thereby allowing the clamping system 2 to share a lifting gripper with the control rod assembly.

[0047] In some embodiments, to facilitate the installation of the compression spring 232 into the first cavity 211, the center tube 21 is processed in sections. After the compression spring 232 is assembled within the inner cavity of the center tube 21, the various sections of the center tube 21 are welded together. Specifically, referring to FIG3 , the center tube 21 includes a first cylindrical body 213 and a second cylindrical body 214, wherein the support plate 22 is fixedly connected to the second cylindrical body 214. The inner cavity of the first cylindrical body 213 includes a first sub-cavity, and the inner cavity of the second cylindrical body 214 includes a second sub-cavity. When the first cylindrical body 213 and the second cylindrical body 214 are connected and assembled to form the center tube 21, the first sub-cavity and the second sub-cavity are connected to form the first cavity 211.

[0048] It should be noted that the clamping rod 231 can be fixedly connected to the first barrel 213 (as shown in FIG4 ) or to the second barrel 214 (as shown in FIG6 ). For ease of explanation, the following uses the example of the clamping rod 231 being integrally formed with the first barrel 213 and the support plate 22 being integrally formed with the second barrel 214 to illustrate the assembly process of the fixed components of the nuclear reactor core. Specifically, the first cylinder 213 and the clamping rod 231 are integrally processed, and the second cylinder 214 and the support plate 22 are integrally processed; the spring seat 233 is assembled into the second sub-cavity of the second cylinder 214, and one end of the spring seat 233 extends from the second sub-cavity; one end of the compression spring 232 is assembled into the first sub-cavity of the first cylinder 213, and the other end is assembled into the second sub-cavity of the second cylinder 214, and its bottom is abutted against the spring seat 233, and then the first cylinder 213 and the second cylinder 214 are ring-welded together to form the first cylinder 213 and the second cylinder 214 to form the center cylinder 21, and the first sub-cavity and the second sub-cavity form the first cavity 211.

[0049] Furthermore, in some embodiments, the second barrel 214 can also be machined in multiple sections. Specifically, the second barrel 214 comprises at least two sub-barrels, each of which has a cavity extending circumferentially therethrough. When the multiple sub-barrels are connected to form the second barrel, the cavities of the multiple sub-barrels are interconnected to form a second sub-cavity, and each pair of sub-barrels is connected by girth welding. For example, as shown in Figure 7, the second barrel 214 comprises three sub-barrels, with the hold-down rod 231 fixedly connected to the first sub-barrel, which is distal to the fuel assembly 3; and the support plate 22 fixedly connected to the third sub-barrel. It should be noted that if the second barrel 214 comprises at least two sub-barrels, the multiple sub-barrels can be first girth-welded to form the second barrel 214, and after the cavities of the multiple sub-barrels are connected to form the second sub-cavity, assembly can then be performed according to the assembly steps described in the above embodiment. Alternatively, the hold-down spring 232 can be first assembled into the cavities of each sub-barrel, and then the multiple sub-barrels can be girth-welded. This is not a limitation.

[0050] Of course, in some embodiments, the first cylinder 213 can also be divided into multiple inner cavity sections, at least one of which is used to place the compression spring 232 first and then perform welding connection.

[0051] It can be understood that the above technical features can be used in any combination without limitation.

[0052] The above are merely embodiments of the present invention and are not intended to limit the patent scope of the present invention. Any equivalent structure or equivalent process transformation made using the contents of the present invention description and drawings, or directly or indirectly applied in other related technical fields, are also included in the patent protection scope of the present invention.

Claims

1. A fixed-type related component of a nuclear reactor core, comprising a functional rod (1) for inserting into a guide tube of a fuel assembly (3) to realize different functions and a clamping system (2) for fixing and connecting the functional rod (1), characterized in that: The pressing system (2) comprises a central tube (21) with an inner cavity and a support plate (22), wherein the support plate (22) is fixedly connected to the central tube (21); The inner cavity of the central tube (21) includes a first cavity (211), the pressing system (2) also includes a pressing structure (23), and the pressing structure (23) includes a pressing rod (231), a pressing spring (232) and a spring seat (233); The compression spring (232) is filled in the first cavity (211), one end of the spring seat (233) is inserted into the first cavity (211) and abuts against the lower end of the compression spring (232), the other end of the spring seat (233) is used to press against the upper tube seat (31) of the fuel assembly (3), the compression rod (231) is fixedly connected to the center tube (21) and is located on a side of the support plate (22) away from the spring seat (233), and the compression rod (231) is used to abut against a side of the core upper plate (4) of the nuclear reactor core close to the fuel assembly (3) to prevent the relevant assembly from moving axially.

2. The fixed related assembly of the nuclear reactor core according to claim 1, characterized in that: A stopper (2111) is provided in the first cavity (211), and the stopper (2111) abuts against the upper end of the compression spring (232).

3. The fixed related assembly of the nuclear reactor core according to claim 1, characterized in that: When the fuel assembly (3) is irradiated and grown in the reactor, and the gap between the fuel assembly (3) and the core upper plate (4) is reduced, the spring seat (233) moves axially along the first cavity (211) in a direction close to the clamping rod (231) to compress the clamping spring (232).

4. The fixed related assembly of a nuclear reactor core according to claim 1, characterized in that: A limiting protrusion (2331) is provided at one end of the spring seat (233) close to the first cavity (211), and a limiting member (2112) is also provided on the cavity wall of the first cavity (211), and the limiting protrusion (2331) abuts against the limiting member (2112) to prevent the spring seat (233) from falling out of the first cavity (211).

5. The fixed related assembly of a nuclear reactor core according to claim 1, characterized in that: The inner cavity of the central tube (21) further comprises a second cavity (212) connected to the first cavity (211); the second cavity (212) is further away from the support plate (22) than the first cavity (211); wherein a hanging groove (2121) is provided on the cavity wall of the second cavity (212).

6. The fixed related assembly of a nuclear reactor core according to claim 1, characterized in that: The central tube (21) comprises a first tube body (213) and a second tube body (214), and the support plate (22) is fixedly connected to the second tube body (214); the inner cavity of the first tube body (213) comprises a first sub-cavity, and the inner cavity of the second tube body (214) comprises a second sub-cavity; when the first tube body (213) and the second tube body (214) are connected and assembled into the central tube (21), the first sub-cavity is connected to the second sub-cavity to form the first cavity (211).

7. The fixed related assembly of the nuclear reactor core according to claim 6, characterized in that: The second cylinder (214) comprises at least two sub-cylinders, each of which has a cavity running through its axial direction, and when a plurality of the sub-cylinders are connected and combined to form the second cylinder (214), the cavities of the plurality of sub-cylinders are connected to form the second sub-cavity.

8. The fixed related assembly of the nuclear reactor core according to claim 6, characterized in that: The first cylinder (213) and the second cylinder (214) are connected by girth welding.

9. The fixed related assembly of a nuclear reactor core according to claim 7, characterized in that: The sub-cylinder bodies are connected by ring welding.

10. The fixed related assembly of a nuclear reactor core according to any one of claims 1 to 9, characterized in that: The support plate (22) is provided with a through hole (221) for coolant to flow through; and / or; The support plate (22) is also provided with a mounting hole (222) for the functional rod (1) to pass through.

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