CN118016328A - Reactor roof structure and reactor roof system - Google Patents

Abstract

The invention relates to a reactor roof structure and a reactor roof system, wherein the reactor roof structure comprises an anti-seismic supporting ring, an anti-seismic plate, a bracket and a flow guide baffle plate, wherein the anti-seismic plate is arranged in the anti-seismic supporting ring, and the flow guide baffle plate is used for dispersing high-temperature air at the center of the reactor roof; the support comprises a plurality of supporting rods which are arranged at intervals, and one end of each supporting rod is fixed with the anti-seismic supporting ring; the flow guide partition plate is arranged on the shock-resistant plate. The reactor roof structure constructed by the invention has the advantages of simple structure, convenient integrated hoisting, convenient maintenance and lighter weight while meeting the integral shock resistance, and can realize cooling through natural circulation of air, thereby avoiding the situation that cables are burnt and trapped in emergency unplanned shutdown accidents.

Description

Reactor roof structure and reactor roof system

Technical Field

The invention relates to the technical field of reactors, in particular to a reactor roof structure and a reactor roof system.

Background

In a nuclear power plant, a reactor roof assembly is one of important parts of a reactor system, is arranged above a reactor pressure vessel roof, is fixed on the reactor pressure vessel roof during normal operation, and is lifted and played back together with the reactor pressure vessel roof and a control rod driving mechanism during shutdown and refueling. However, as the control rod driving mechanism is internally provided with a high-temperature heat source, the generated high-temperature air flow can cause the heat in the pile top to be difficult to dissipate, and the local environment temperature of each part (such as a cable and the like) in the pile top is too high, so that the risk of emergency unplanned shutdown accidents caused by burning exists.

In order to solve the problem, the existing pile top structure is correspondingly provided with a forced ventilation cooling device, but the forced ventilation cooling device occupies a large amount of space of the pile top, so that the pile top structure is complex, and the difficulty of pile top structure arrangement and cable laying and the operation and maintenance cost are increased. And makes the stack-top structure too dependent on the device, once it fails to function properly, it will again fall into the potential environment of an emergency unplanned shutdown event.

At present, the existing pile top structure comprises a distributed pile top structure and an integrated pile top structure, the distributed pile top structure is provided with an anti-vibration supporting component for carrying out anti-vibration supporting on a control rod driving mechanism, the pile top structure is distributed, a plurality of anti-vibration pull rods are needed for connecting and fixing the anti-vibration supporting component arranged on the pile top structure, but the independent distributed structure of the anti-vibration pull rods enables the independent distributed structure of the anti-vibration pull rods to occupy a critical path for material changing overhaul every time of lifting and lowering, integral lifting of the pile top structure cannot be achieved, and irradiation dose of operators is increased. The integral pile top structure is integrally in a cylinder shape, the structural arrangement of the integral pile top structure leads to the remarkable increase of the pile top weight, and as no corresponding anti-seismic pull rod is arranged, the anti-seismic design difficulty is increased, the pile top structure in a cylinder shape seals equipment such as a control rod driving mechanism, a pipeline of a forced ventilation cooling device, an instrument tube seat and the like inside, and the difficulty of in-service maintenance and replacement is remarkably increased.

Disclosure of Invention

The invention aims to solve the technical problem of providing a reactor roof structure and a reactor roof system.

The invention adopts the following technical scheme:

A reactor roof structure is constructed comprising an earthquake resistant support ring and an earthquake resistant plate mounted within the earthquake resistant support ring, further comprising:

the support comprises a plurality of support rods which are arranged at intervals, and one end of each support rod is fixed with the anti-seismic support ring;

the flow guide partition plate is used for dispersing high-temperature air at the center of the top of the pile and is arranged on the anti-seismic plate.

In some embodiments, the support further comprises a plurality of connecting pieces, and two ends of each connecting piece are respectively fixed with any two adjacent supporting rods.

In some embodiments, the connecting members include a plurality of first connecting members disposed horizontally and a plurality of second connecting members disposed obliquely, the support bars are disposed vertically, a plurality of first connecting members and a plurality of second connecting members are disposed between any two adjacent support bars at intervals, and the first connecting members and the second connecting members between any two adjacent support bars are disposed crosswise.

In some embodiments, the support rods are uniformly spaced along the circumference of the anti-seismic support ring, the first and second connectors are each rod-shaped, and each adjacent first and second connector and support rod define a right triangle.

In some embodiments, the reactor roof structure further comprises a base to which the other end of the support rod is fixed.

In some embodiments, the base includes a base body having a flange ring shape, and an upper end portion and a lower end portion of the base body protrude outward in a circumferential direction.

In some embodiments, the baffle is disposed coaxially with the shock-resistant plate.

In some embodiments, the distance between the baffle and the shock-resistant plate is 0-400mm.

In some embodiments, the side length or diameter of the baffle is 200-2000mm.

In some embodiments, the baffle plate is formed with a plurality of relief holes for receiving a control rod drive mechanism.

In some embodiments, the baffle is formed by splicing at least two splicing substrates, at least one relief groove is formed on the edge of each splicing substrate, and the relief holes are formed by splicing two corresponding relief grooves.

In some embodiments, the reactor roof structure further comprises a cable tray and cable bridge assembly mounted above the baffle plate and an upper hanger connected with the cable tray and cable bridge assembly.

A reactor roof system is constructed to be disposed on a reactor pressure vessel roof and includes the reactor roof structure of any one of the above and a control rod drive mechanism.

In some embodiments, the other end of the support rod is connected to the reactor pressure vessel head, and the control rod drive mechanism is disposed through the reactor head.

In some embodiments, the reactor roof structure further comprises a base to which the other end of the support rod is fixed, the base being mounted to the reactor pressure vessel roof by at least one support.

In some embodiments, the control rod drive mechanism and at least a portion of the cable routed to the stacking head system are made of a high temperature resistant material.

The implementation of the invention has at least the following technical effects:

According to the reactor roof structure constructed by the invention, the integrated hoisting is realized by arranging the bracket, so that the vibration-resistant pull rod does not occupy a critical path for major repair of the reload, and the closed ring is not formed, so that the maintenance and the replacement are difficult, the integral vibration resistance is met, and meanwhile, the structure is simple, the integrated hoisting is convenient, the maintenance is convenient, and the weight is light;

According to the invention, the flow guide partition plates are arranged, so that a forced ventilation cooling device is not required to be arranged on the reactor roof structure, the space arrangement pressure of the reactor roof is reduced, the cable laying difficulty and the operation and maintenance cost are reduced, the cooling can be realized through natural circulation of air, and the situation that the cable is burnt and falls into an emergency unplanned shutdown accident is avoided.

Drawings

In order to more clearly illustrate the technical solution of the present invention, the following description will be given with reference to the accompanying drawings and examples, it being understood that the following drawings only illustrate some examples of the present invention and should not be construed as limiting the scope, and that other related drawings can be obtained from these drawings by those skilled in the art without the inventive effort. In the accompanying drawings:

FIG. 1 is a schematic perspective view of a stacking system according to an embodiment of the present invention;

FIG. 2 is a schematic illustration of the assembled structure of the shock-resistant support rings, shock-resistant plates and baffles in the stacking system of FIG. 1;

FIG. 3 is a schematic view of a partial structure of a control rod drive mechanism and rod control and rod position system in the stacking system of FIG. 1.

Detailed Description

For a clearer understanding of technical features, objects and effects of the present invention, a detailed description of embodiments of the present invention will be made with reference to the accompanying drawings. In the following description, it should be understood that the directions or positional relationships indicated by "front", "rear", "upper", "lower", "left", "right", "vertical", "horizontal", "bottom", "inner", "outer", etc. are configured and operated in specific directions based on the directions or positional relationships shown in part of the drawings, are merely for convenience of description of the present invention, and do not indicate that the apparatus or element to be referred to must have specific directions, and thus should not be construed as limiting the present invention.

It should also be noted that unless explicitly stated or limited otherwise, terms such as "mounted," "connected," "secured," "disposed," and the like are to be construed broadly and may be, for example, fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communicated with the inside of two elements or the interaction relationship of the two elements. When an element is referred to as being "on" or "under" another element, it can be "directly" or "indirectly" on the other element or one or more intervening elements may also be present. The terms "first," "second," and the like are used merely for convenience in describing the present technology and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated, whereby features defining "first," "second," and the like may explicitly or implicitly include one or more such features. The specific meaning of the above terms in the present invention can be understood by those of ordinary skill in the art according to the specific circumstances.

In the following description, for purposes of explanation and not limitation, specific details are set forth such as the particular system architecture, techniques, etc., in order to provide a thorough understanding of the embodiments of the present invention. It will be apparent, however, to one skilled in the art that the present invention may be practiced in other embodiments that depart from these specific details. In other instances, 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.

Fig. 1 shows a reactor head 1 in an embodiment of the invention for providing shock-resistant support for a control rod drive mechanism 3 that can limit excessive deformation of the CRDM during seismic conditions to maintain its normal function, ensuring its functional integrity during accident conditions. And also serves to provide a cooling and ventilating passage for the yoke coil of the control rod driving mechanism 3 to ensure the normal operation of the control rod driving mechanism 3. The reactor roof structure 1 is arranged above the reactor pressure vessel head 2 for integral lifting with the reactor pressure vessel head 2 and the control rod drive mechanism 3 during reactor refueling and servicing.

The reactor roof structure 1 comprises a bracket 10, an anti-seismic support ring 30, anti-seismic plates 40, a flow guide baffle 50, cable brackets, a cable bridge assembly 60 and an upper lifting tool 70, wherein the bracket 10 comprises a plurality of support rods 11 which are arranged at intervals, one end of each support rod 11 is fixed with the anti-seismic support ring 30, and the other end is connected with a reactor pressure vessel top cover 2. The seismic plate 40 is plate-shaped and is mounted in the seismic support ring 30. The baffle 50 is disposed on the shock-resistant plate 40, and is used for dispersing high-temperature air at the center of the top of the pile, so as to avoid direct contact between the high-temperature air and the cable at the center of the top of the pile, and to generate local high-temperature damage to the cable performance. The cable tray and cable bridge assembly 60 is mounted above the baffle 50 for routing all of the rod control and rod position system cables 4, core measurement system cables, take-off components and vibration monitoring system cables in the top region of the stack to the prescribed civil interface. The upper spreader 70 is connected to the cable tray and cable bridge assembly 60 for handling the reactor roof structure 1 during reactor refueling and servicing.

The support rods 11 of the support 10 are all in a longitudinal shape and are arranged at intervals, and two ends of each support rod 11 are connected with the anti-seismic support ring 30 and the reactor pressure vessel top cover 2 for anti-seismic support, and play a role of a lower suspender in the hoisting process, so that integrated hoisting can be realized. The bracket 10 further includes a plurality of connection members, both ends of each of which are respectively fixed to any adjacent two of the support bars 11, so as to enhance the supporting strength of the bracket 10. The bracket 10 structure not only provides an arrangement space for the control rod driving mechanism 3, but also provides enough rigidity for the reactor pressure vessel top cover 2 and the control rod driving mechanism 3 under the earthquake working condition, and prevents the control rod driving mechanism 3 from excessively deforming so as to maintain the normal function; but also can ensure the natural cooling ventilation of the top area of the pile, and avoid the situation that the local temperature of the top area of the pile is too high to be difficult to be scattered.

In some embodiments, each support rod 11 is disposed vertically between the shock resistant support ring 30 and the reactor pressure vessel head 2. The connecting piece includes first connecting piece 12 and second connecting piece 13, and wherein this first connecting piece 12 level sets up, and this second connecting piece 13 slope sets up for prevent that the device from inefficacy when meetting the operating mode of earthquake side-to-side swing, further improve the stability of reactor roof structure 1. At least one first connecting piece 12 and at least one second connecting piece 13 are arranged between any two adjacent supporting rods 11, and two ends of each first connecting piece 12 and two ends of each second connecting piece 13 are respectively connected with the two adjacent supporting rods 11.

Specifically, a plurality of first connection members 12 and a plurality of second connection members 13 may be provided between any adjacent two of the support bars 11, and the first connection members 12 and the second connection members 13 between any adjacent two of the support bars 11 are alternately provided.

In the present embodiment, the support rods 11 are arranged at uniform intervals in the circumferential direction of the vibration-resistant support ring 30 such that a plurality of first and second connection members 12 and 13 are connected to both sides of each support rod 11. And each of the adjacent first and second connection members 12 and 13 defines a right triangle with the support bar 11.

It is to be understood that "adjacent" herein refers to the first connection 12 between two adjacent support bars 11 and the second connection 13 being adjacent one above the other.

In some embodiments, the support bars 11 may be composed of square or round steel, preferably 6-10 in number, and preferably 30-200 mm in side length (for support bars 11 composed of square steel) or diameter (for support bars 11 composed of round steel).

In some embodiments, between any adjacent two support bars 11, preferably 5-10 first connectors 12 and 5-10 second connectors 13. Wherein the first connecting piece 12 and/or the second connecting piece may consist of angle steel or may consist of flat steel, the width of which is preferably 30mm-150mm.

In some embodiments, the bracket 10 may also be replaced with a pull rod structure.

In some embodiments, the reactor roof structure 1 further comprises a base 20 for increasing the strength of the seismic support of the reactor roof structure 1. Specifically, the base 20 includes a base 21, the base 21 is in a flange ring shape, the upper end and the lower end of the base 21 are protruded outwards along the circumferential direction, the lower end of each supporting rod 11 is fixed on the upper end surface of the base 21, so as to effectively increase the anti-seismic supporting rigidity, reduce the load (moment) while reducing the center of gravity of the reactor roof structure 1, and prevent the overall weight of the reactor roof structure 1 from being too large.

In some embodiments, the base 20 further comprises at least one support 22, the base 21 being secured to the reactor pressure vessel head 2 by the support 22.

In this embodiment, the number of the supporting pieces 22 may be plural, preferably 4 to 10. The plurality of support pieces 22 are provided at intervals in the circumferential direction of the lower end portion of the base 21, and are connected to the reactor pressure vessel header 2.

In the present embodiment, the supporting member 22 is a skirt structure, and the plurality of supporting members 22 are uniformly spaced apart from each other in the circumferential direction of the lower end portion of the base 21.

In some embodiments, the height of the seat 21 in the axial direction is preferably 200mm-2000mm.

It will be appreciated that the overall height of the support bar 11 and base 20 is adapted to the height of the control rod drive mechanism 3, and that the heights of both the base 20 and the support bar 11 can be flexibly adjusted.

Referring to fig. 2 together, in this embodiment, the anti-seismic support ring 30 is annular, the anti-seismic plate 40 is circular, the outer diameter of the anti-seismic plate 40 is adapted to the inner diameter of the anti-seismic support ring 30, and the anti-seismic plate 40 is fixed in the anti-seismic support ring 30. The shock-resistant plate 40 has a plurality of receiving holes penetrating therethrough in a thickness direction for the control rod driving mechanism 3 to penetrate therethrough.

It should be understood that the shape of the shock-resistant support ring 30 and the shock-resistant plate 40 is not limited to a circle, and may be provided in any shape such as a square, a polygon, etc. The shock-resistant support ring 30 may be of solid construction, and may also be of hollow box construction.

The shock resistant support ring 30 plus shock resistant plate 40 plus bracket 10 plus base 20 integrally form a "drum-net" support structure having a number of beneficial effects including, but not limited to: first, this bearing structure has realized the integrated design of heap top, only need when hoist and mount, playback can realize the integral hoisting of reactor roof structure 1 through the hoist and mount to upper portion hoist 70, avoided the installation of a plurality of hoisting structures, need not to occupy the critical route of reloading overhaul, the operation is more simple and convenient, has reduced operating personnel's irradiation dose, and the degree of difficulty of in-service maintenance, change reduces. Secondly, the integral anti-seismic design is realized by a smaller weight structure, the weight of the pile top is reduced, the anti-seismic allowance is improved, the pile top can be supported, enough rigidity can be provided for the pile top and the control rod driving mechanism 3 under the earthquake working condition, the control rod driving mechanism 3 is limited to excessively deform so as to maintain the normal function of the control rod driving mechanism, and the functional integrity of the control rod driving mechanism under the earthquake working condition is ensured. Third, the integrated support structure provides the reactor roof structure 1 with the possibility of modularity (off-island assembly and integral hoisting).

In some embodiments, the baffle 50 is disposed at the center of the shock-resistant plate 40, and is used for blocking the high-temperature air concentrated at the center of the top of the stack, which is formed by the control rod driving mechanism 3, so as to avoid the high-temperature air at the center of the top of the stack from directly contacting with the cable at the center of the top of the stack, thereby damaging the cable due to local excessive temperature. Meanwhile, the flow guide partition 50 can guide the high-temperature air rising to the central position of the top of the stack to the secondary central position, so that the high-temperature air originally concentrated to the central position rises is diffused all around along the circumferential direction, the airflow circulation length of the high-temperature air is prolonged, the dispersing area of the high-temperature air is enlarged, the effect of avoiding local high temperature is achieved, and the cable laid at the central position in the cable bracket and the cable bridge assembly 60 is further prevented from being damaged by the high-temperature air.

It should be understood that, since the high temperature coil in the control rod driving mechanism 3 emits a large amount of heat, the control rod driving mechanism 3 located in the bracket 10 generates a heat island effect, a large amount of high temperature air is concentrated and spread upwards toward the central position (central axis position), a local high temperature area is concentrated, and since a gap is formed between the accommodating hole on the shock-resistant plate 40 and the control rod driving mechanism 3, the high temperature air continues to rise along the accommodating hole, which affects the cable bracket located above and the cable laid at the central position in the cable bridge assembly 60, resulting in damage.

The "center position" is a region in which the central axis of the control rod driving mechanism 3 (the central axis of the reactor roof structure 1 and the seismic plates 40 and the seismic support rings 30 in this embodiment) is within a small area, and in this embodiment, the region covered by the baffle plate 50. Correspondingly, the "sub-center position" described above is the remaining position that is not listed as the center position.

In some embodiments, the baffle 50 may be circular, rectangular, polygonal, or other irregular shape, with sides (when the baffle 50 is rectangular) or diameters (when the baffle 50 is circular) of preferably 200-2000mm.

In some embodiments, the baffle 50 may be disposed in contact with the shock-resistant plate 40 or may be disposed in a spaced apart relationship, preferably 0mm to 400mm. The reactor roof structure 1 further includes a plurality of connectors (not shown) for fixing the baffle 50 to the upper end surface of the shock-resistant plate 40. In some embodiments, the connection may be selected to be adjustable so that the distance between the shock panel 40 and the baffle 50 is adjustable. In this embodiment, the connector is an adjusting bolt.

It should be understood that the connecting member may be fixed by other structures, and the distance between the baffle 50 and the shock-resistant plate 40 may be controlled by providing a local protrusion structure between the two structures.

In some embodiments, the thickness of the baffle 50 is preferably 5mm to 50mm.

In some embodiments, a plurality of relief holes 52 are formed in the thickness direction of the baffle 50 for accommodating the upper end portion of the control rod driving mechanism 3. The shape and position of the relief holes 52 are adapted to the control rod driving mechanism 3 to ensure that the high temperature air flow does not pass through the relief holes 52 into the cable tray and cable bridge assembly 60 above.

It should be understood that, when the upper end of the control rod driving mechanism 3 is located at a horizontal position lower than the horizontal position of the baffle 50, the baffle 50 may not be provided with the relief hole 52.

In some embodiments, the baffle 50 is formed by splicing at least two splice substrates 51, and at least one relief groove is formed at the edge of each splice substrate 51, and the corresponding relief grooves on two adjacent splice substrates 51 are spliced with each other to form the relief hole 52. To improve the ease of assembly and disassembly of the reactor roof structure 1 and to facilitate its assembly and disassembly when it is necessary to replace the components in the control rod drive mechanism 3.

In this embodiment, the baffle 50 is made of a metal material, and is disposed coaxially with the shock-resistant plate 40, and has a rectangular shape as a whole. The four splice substrates 51 are spliced to form the splice device, each splice substrate 51 is provided with a plurality of abdication grooves, and the corresponding abdication grooves are respectively spliced to form a plurality of abdication holes 52.

This arrangement of baffle 50 has a number of beneficial effects including, but not limited to: firstly, the reactor roof structure 1 can ensure the whole operation performance of the control rod driving mechanism 3 without arranging a forced ventilation cooling system, reduce the burning probability and the unplanned shutdown probability of coil components caused by the failure of a cooling ventilation device, improve the reliability and the economy of the operation of a nuclear power station, and can normally operate in natural ventilation cooling under the working conditions of normal operation of the reactor, shutdown and refueling and the like. Secondly, the forced ventilation cooling system is not arranged, the overall weight of the reactor roof structure 1 is reduced, the gravity center of the reactor roof structure is lowered, meanwhile, the arrangement of cables on the roof is facilitated, the ventilation related structure is not required to be removed during shutdown and refueling, and the overhaul refueling period is saved. Third, the baffle 50 cooperates with the support structure integrally formed by the anti-seismic support ring 30, the anti-seismic plate 40, the bracket 10 and the base 20, so that the high-temperature air blocked by the baffle 50 is located below the baffle 50, and the heat dissipation effect of the reactor roof structure 1 can be further improved by natural ventilation and dispersion.

In some embodiments, the cable tray and cable bridge assembly 60, upper spreader 70, shock resistant support ring 30, and shock resistant plate 40 may all be implemented using conventional techniques.

It should be understood that the above-mentioned "fixing" may be fixed by welding, may be fixed by fastening (bolting or riveting), and may be fixed by an integral molding process, which is not particularly limited herein.

It should be understood that the numerical ranges set forth above include the present numbers.

As further shown in fig. 1, the present invention further constructs a reactor roof system disposed on a reactor pressure vessel top cover 2, comprising any of the reactor roof structures 1 described above and a control rod driving mechanism 3, wherein the control rod driving mechanism 3 is disposed through the reactor roof structure 1.

Referring also to FIG. 3, in some embodiments, the control rod driving mechanism 3 may be made of a high temperature resistant material to improve the operation of the control rod driving mechanism 3 and prevent burnout by high temperature air.

In some embodiments, the cables in the reactor roof structure 1 and at least some of the cables disposed within the cable bridge assembly 60 are also made of a high temperature resistant material for improving the performance of the cables to avoid burnout by high temperature air.

Specifically, in the present embodiment, the rod control and rod position system cable 4 disposed within the cable and cable bridge assembly 60 is made of a high temperature resistant material.

It is to be understood that the above examples only represent preferred embodiments of the present invention, which are described in more detail and are not to be construed as limiting the scope of the invention; it should be noted that, for a person skilled in the art, the above technical features can be freely combined, and several variations and modifications can be made without departing from the scope of the invention; therefore, all changes and modifications that come within the meaning and range of equivalency of the claims are to be embraced within their scope.

Claims (16)

1. A reactor roof structure comprising an anti-seismic support ring (30) and an anti-seismic plate (40), said anti-seismic plate (40) being mounted in said anti-seismic support ring (30), characterized in that it further comprises:

The support (10) comprises a plurality of supporting rods (11) which are arranged at intervals, and one end of each supporting rod (11) is fixed with the anti-vibration supporting ring (30);

And the guide clapboard (50) is used for dispersing high-temperature air at the center of the top of the pile, and the guide clapboard (50) is arranged on the anti-seismic plate (40).

2. The reactor roof structure according to claim 1, characterized in that said support (10) further comprises a plurality of connection members, the two ends of which are respectively fixed to any adjacent two of said support bars (11).

3. The reactor roof structure according to claim 2, characterized in that the connection members comprise a plurality of horizontally arranged first connection members (12) and a plurality of obliquely arranged second connection members (13), the support bars (11) are all vertically arranged, a plurality of first connection members (12) and a plurality of second connection members (13) are arranged between any adjacent two support bars (11) at intervals, and the first connection members (12) and the second connection members (13) between any adjacent two support bars (11) are arranged in a crossing manner.

4. The reactor roof structure according to claim 2, characterized in that the support rods (11) are uniformly spaced along the circumference of the seismic support ring (30), the first and second connection members (12, 13) each being rod-shaped, each adjacent first and second connection member (12, 13) defining a right triangle with the support rods (11).

5. The reactor roof structure according to claim 1, further comprising a base (20), the other end of the support rod (11) being fixed to the base (20).

6. The reactor roof structure according to claim 5, wherein the base (20) includes a base body (21), the base body (21) having a flange ring shape, and an upper end portion and a lower end portion thereof are protruded outwardly in a circumferential direction.

7. The reactor roof structure according to claim 1, characterized in that the baffle plate (50) is arranged coaxially to the shock-resistant plate (40).

8. The reactor roof structure according to claim 1, characterized in that the distance between the baffle plate (50) and the shock-resistant plate (40) is 0-400mm.

9. The reactor roof structure according to claim 1, characterized in that the side length or diameter of the baffle plate (50) is 200-2000mm.

10. The reactor roof structure according to claim 1, characterized in that the baffle plate (50) is formed with a plurality of relief holes (52) for receiving control rod driving mechanisms (3).

11. The reactor roof structure according to claim 10, wherein the baffle plate (50) is formed by splicing at least two splice substrates (51), at least one relief groove is formed on an edge of each splice substrate (51), and two corresponding relief grooves are spliced to form the relief hole (52).

12. The reactor roof structure according to claim 1, further comprising a cable tray and cable bridge assembly (60) and an upper hanger (70), the cable tray and cable bridge assembly (60) being mounted above the deflector (50), the upper hanger (70) being connected to the cable tray and cable bridge assembly (60).

13. A reactor roof system provided on a reactor pressure vessel head (2), characterized by comprising a reactor roof structure according to any one of claims 1-12 and a control rod drive mechanism (3).

14. The reactor head system according to claim 13, wherein the other end of the support rod (11) is connected to the reactor pressure vessel head (2), and the control rod drive mechanism (3) is disposed through the reactor head structure (1).

15. The reactor head system according to claim 14, characterized in that the reactor head structure (1) further comprises a base (20), the other end of the support rod (11) being fixed to the base (20), the base (20) being mounted to the reactor pressure vessel head (2) by means of at least one support (22).

16. The stacking system as claimed in claim 13, characterized in that the control rod drive mechanism (3) and at least part of the cables routed by the stacking system are made of a high-temperature resistant material.