Coolant bypass flow control method and leak tightness test device for high-temperature gas cooled reactor

Abstract

A coolant bypass flow control method and leak tightness test device for a high-temperature gas cooled reactor. The coolant bypass flow leak tightness test device for a high-temperature gas cooled reactor comprises a reactor unit (100), which comprises a protective layer (101) and a plurality of groups of graphite blocks (102); a blocking unit (200), which comprises longitudinal sealing members (201) and transverse sealing racks (202); and an adjusting unit (300), which comprises a plurality of rotating rods (301), a transmission member (302) which is arranged on one side of the rotating rods, and a limiting cover (303). Testing of the leak tightness is conducted by means of a simulation experiment device, and the longitudinal bypass flow and transverse leakage flow of a helium coolant are blocked, thereby reducing the effect of structural bypass flow on the flow distribution of the helium coolant within a pebble bed, ensuring an effective flow rate of the coolant flowing through the pebble bed, and thus optimizing the temperature distribution within the pebble bed and the maximum temperature of fuel, thereby providing support for the design and justification of the reactor structure of the high-temperature gas cooled reactor, further improving the safety and reliability of the pebble bed high-temperature gas cooled reactor.

Description

A high-temperature gas-cooled reactor coolant bypass flow control method and sealing test device Technical Field

[0001] The present invention relates to the technical field of bypass flow control, in particular to a method for controlling the bypass flow of a coolant in a high-temperature gas-cooled reactor and a sealing inspection device thereof. Background Art

[0002] The pebble-bed high-temperature gas-cooled reactor (HTGR) is an advanced reactor with inherent safety, high power generation efficiency, and a wide range of potential thermal applications. The reactor's internal components consist of numerous ceramic components, such as graphite blocks and carbon blocks, which serve as both the reactor's structural materials and the flow paths for the helium coolant. Based on the flow characteristics and generation of the coolant within each part of the reactor, the helium coolant can be divided into three components:

[0003] 1. Helium mainstream refers to the effective flow portion that flows through the core pebble bed and carries the heated fuel out of the core;

[0004] 2. Functional bypass flow, including bypass flow through the control rod hole and bypass flow through the discharge pipe;

[0005] 3. Structural bypass flow: Due to assembly, thermal expansion and other reasons, there will be certain narrow gaps between the graphite blocks of the in-core components. As a result, while helium flows in the main design flow channel, a small part of it will flow in the graphite gaps, becoming a bypass flow of the mainstream helium.

[0006] The existence of structural bypass flow changes the flow distribution of helium coolant in the reactor to a certain extent, resulting in a decrease in the effective helium coolant flow through the pebble bed, which in turn affects the temperature distribution in the pebble bed and the maximum temperature of the fuel. Therefore, it is necessary to focus on and effectively control it in the design of high-temperature gas-cooled reactors. There is a vertical narrow gap between every two graphite blocks in the graphite side reflector layer, and the narrow gap runs through the entire side reflector layer, which is one of the typical bypass flow channels. In order to deal with the structural bypass flow flowing through the vertical narrow gap between the graphite blocks in the side reflector layer inside the reactor, we need a bypass flow control device and a sealing performance simulation test device to optimize the helium coolant flow distribution in the reactor and effectively control the maximum temperature of the fuel, thereby effectively supporting the design and demonstration of the high-temperature gas-cooled reactor structure and further improving the safety and reliability of the pebble bed high-temperature gas-cooled reactor. Therefore, we conceived and designed the simulation test device and its bypass flow control method to propose the present invention.

[0007] Summary of the Invention

[0008] The purpose of this section is to summarize some aspects of the embodiments of the present invention and briefly introduce some preferred embodiments. Some simplifications or omissions may be made in this section and the abstract and title of this application to avoid obscuring the purpose of this section, the abstract and the title of the invention, and such simplifications or omissions should not be used to limit the scope of the present invention.

[0009] In view of the above problems or problems existing in the prior art, the present invention is proposed.

[0010] Therefore, the purpose of the present invention is to provide a bypass flow control device and a sealing performance simulation test device for the structural bypass flow flowing through the vertical narrow gaps between the graphite blocks in the reflective layer on the inner side of the reactor, so as to optimize the helium coolant flow distribution in the reactor, effectively control the maximum temperature of the fuel, and ultimately optimize the helium coolant flow distribution in the pebble bed.

[0011] To solve the above technical problems, the present invention provides the following technical solution: a method for controlling coolant bypass flow in a high-temperature gas-cooled reactor, comprising the following steps:

[0012] S1. Identify the structural bypass locations within the reactor;

[0013] S2. Construct a dovetail groove structure sealing key to seal the bypass channel;

[0014] S3. Carry out side flow sealing performance test on the processing simulation body to verify the side flow control effect.

[0015] As a preferred solution of the method for controlling coolant bypass flow in a high-temperature gas-cooled reactor described in the present invention, the identification of structural bypass flow in the reactor is specifically as follows: according to the structural characteristics of the reactor, the narrow gap bypass flow that may affect the temperature distribution of the pebble bed is analyzed, and through thermal-hydraulic calculations, the size of the bypass flow and its influence on the flow and heat transfer in the pebble bed are quantitatively analyzed, thereby confirming the main narrow gap bypass flow.

[0016] As a preferred embodiment of the method for controlling coolant bypass flow in a high-temperature gas-cooled reactor described in the present invention, the design of the dovetail groove structure sealing key is specifically to design a dovetail groove structure sealing key on the ball bed side of the identified narrow gap, including a horizontal sealing key for sealing the narrow gap on the upper surface between the graphite blocks and a vertical sealing key for sealing the vertical narrow gap between the graphite blocks that passes through the entire side reflection layer, thereby preventing the longitudinal bypass flow and lateral leakage of the helium coolant.

[0017] Another object of the present invention is to provide a high temperature gas cooled reactor bypass flow tightness testing device, comprising a reactor unit, a protective layer, and a plurality of groups of graphite blocks disposed within the protective layer;

[0018] A sealing unit comprising a longitudinal sealing member and a transverse sealing rack provided on one side of the longitudinal sealing member;

[0019] The adjustment unit includes a plurality of rotating rods, a transmission member arranged on one side of the rotating rods, and a limiting cover arranged on one side of the transmission member.

[0020] As a preferred embodiment of the high temperature gas-cooled reactor bypass leak tightness test device of the present invention, the protective layer includes a mounting groove provided at the bottom thereof;

[0021] The installation slot includes a compression spring arranged inside the installation slot and a plurality of fixed guide balls arranged on the inner wall of the installation slot.

[0022] As a preferred solution of the high-temperature gas-cooled reactor bypass flow sealing test device of the present invention, the graphite block includes a bypass flow channel and a trapezoidal protrusion arranged on one side of the graphite block.

[0023] As a preferred embodiment of the device for testing the sidestream sealing performance of a high-temperature gas-cooled reactor according to the present invention, the cross-sectional shape of the longitudinal sealing member is consistent with the gap formed between the two adjacent graphite blocks on the same plane;

[0024] The longitudinal sealing member includes a first inserting groove longitudinally arranged inside the longitudinal sealing member, and a second inserting groove transversely arranged inside the longitudinal sealing member;

[0025] The aperture of the upper half of the first plug-in slot gradually decreases from top to bottom. The first plug-in slot also includes a spiral groove arranged on its inner wall, and an annular groove connected to and arranged below the spiral groove.

[0026] As a preferred embodiment of the high-temperature gas-cooled reactor bypass seal inspection device of the present invention, the rotating rod includes a pressing knob, a pressing spring provided on one side of the pressing knob, a first plug provided on one side of the pressing spring, a second plug provided on one side of the first plug, a gear provided on an outer wall of the second plug, and a clamp provided on one side of the second plug;

[0027] The diameter of the first insertion rod gradually decreases from top to bottom, and the first insertion rod further includes a spherical protrusion arranged on the outer wall thereof.

[0028] As a preferred solution of the high-temperature gas-cooled reactor bypass sealing test device of the present invention, the transmission member includes a disc gear, a connecting rod arranged on one side of the disc gear, and a rotating rod arranged on one side of the connecting rod.

[0029] As a preferred solution of the high-temperature gas-cooled reactor bypass sealing inspection device of the present invention, the limiting cover includes a plurality of limiting protrusions arranged on one side thereof.

[0030] The beneficial effects of the present invention are as follows: the present invention designs a dovetail groove structural seal at the main narrow slit bypass position, which forms a barrier to the longitudinal bypass flow and lateral leakage of the helium coolant. At the same time, a bypass sealing performance test device is designed to verify the bypass control effect. Through the above-mentioned bypass control measures, the influence of structural bypass flow on the helium coolant flow distribution in the pebble bed is effectively reduced, the effective coolant flow through the pebble bed is guaranteed, and the temperature distribution of the pebble bed and the maximum temperature of the fuel are optimized, thereby effectively supporting the design and demonstration of the high-temperature gas-cooled reactor structure and further improving the safety and reliability of the pebble-bed high-temperature gas-cooled reactor. BRIEF DESCRIPTION OF THE DRAWINGS

[0031] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the following briefly introduces the drawings required for describing the embodiments. Obviously, the drawings described below are only some embodiments of the present invention. Those skilled in the art can also derive other drawings based on these drawings without inventive effort. Among them:

[0032] FIG1 is a schematic diagram of the overall structure of a high-temperature gas-cooled reactor bypass leak tightness test device;

[0033] FIG2 is another schematic diagram of the overall structure of the high-temperature gas-cooled reactor bypass leak tightness test device;

[0034] FIG3 is an overall cross-sectional view of a high-temperature gas-cooled reactor bypass leak tightness test device;

[0035] FIG4 is a partial enlarged view of the bypass flow sealing test device for a high temperature gas-cooled reactor at point A in FIG3 ;

[0036] FIG5 is a schematic diagram of the structure of the rotating rod in the high-temperature gas-cooled reactor bypass sealing test device;

[0037] FIG6 is a schematic diagram of the structure of a graphite block in a high-temperature gas-cooled reactor side-flow sealing test device;

[0038] Figure 7 is a schematic diagram of the structure of the longitudinal seal in the high-temperature gas-cooled reactor bypass sealing test device. DETAILED DESCRIPTION

[0039] In order to make the above-mentioned objects, features and advantages of the present invention more obvious and easy to understand, the specific embodiments of the present invention are described in detail below with reference to the accompanying drawings.

[0040] In the following description, many specific details are set forth to facilitate a full understanding of the present invention. However, the present invention may also be implemented in other ways different from those described herein. Those skilled in the art may make similar generalizations without violating the connotation of the present invention. Therefore, the present invention is not limited to the specific embodiments disclosed below.

[0041] Secondly, the term "one embodiment" or "embodiment" herein refers to a specific feature, structure, or characteristic that may be included in at least one implementation of the present invention. The phrase "in one embodiment" appearing in various places throughout this specification does not necessarily refer to the same embodiment, nor does it refer to a separate or selective embodiment that is mutually exclusive of other embodiments.

[0042] Example 1

[0043] A first embodiment of the present invention provides a device for testing the sidestream tightness of a high-temperature gas-cooled reactor, which includes the following steps:

[0044] S1. Identify the structural bypass locations within the reactor;

[0045] S2. Construct a dovetail groove structure sealing key to seal the bypass channel;

[0046] S3. Carry out side flow sealing performance test on the processing simulation body to verify the side flow control effect.

[0047] To identify structural bypass flows in the reactor, specifically, based on the structural design features of the reactor, the narrow gap bypass flows that may affect the temperature distribution of the pebble bed are analyzed, and through thermal hydraulic calculations, the size of the bypass flows and their impact on the flow and heat transfer in the pebble bed are quantitatively analyzed, thereby confirming the main narrow gap bypass flows.

[0048] Specifically, a dovetail groove structure sealing key is designed on the ball bed side of the identified narrow gap, including a horizontal sealing key for sealing the narrow gap on the upper surface between the graphite blocks and a vertical sealing key for sealing the vertical narrow gap between the graphite blocks that passes through the entire side reflection layer, thereby blocking the longitudinal bypass and lateral leakage of the helium coolant.

[0049] It should be noted that adjacent sealing keys are secured by overlapping mortise and tenon structures. The transverse sealing keys are secured by the mortise and tenon structure to prevent radial movement, while the vertical sealing keys are secured by a dovetail groove structure and the mortise and tenon structure between the upper and lower keys to prevent them from falling into the ball bed.

[0050] Preferably, a 1:10 reactor dummy is fabricated. A channel extending through the narrow slit is machined into the graphite block anti-rotation key, and a sealing cover is added to seal the cavity between the outer cylinder and the side reflector graphite block. A blower is then used to extract the bypass flow into the narrow slit, and the measured bypass flow rate is compared with the upper limit of the reactor design leakage rate to verify the effectiveness of bypass flow control. Because the medium flowing through the reactor is air at room temperature and pressure, the design leakage rate must be converted from the value corresponding to high-temperature, high-pressure helium to that of air at room temperature and pressure.

[0051] In summary, the present invention designs a dovetail groove structure sealing key at the main narrow slit bypass position to block the longitudinal bypass flow and lateral leakage of the helium coolant. At the same time, a bypass sealing performance test device is designed to verify the bypass control effect. Through the above-mentioned bypass control measures, the influence of structural bypass flow on the helium coolant flow distribution in the pebble bed is effectively reduced, and the effective coolant flow through the pebble bed is guaranteed, thereby optimizing the temperature distribution of the pebble bed and the maximum temperature of the fuel, thereby effectively supporting the design and demonstration of the high-temperature gas-cooled reactor structure and further improving the safety and reliability of the pebble-bed high-temperature gas-cooled reactor.

[0052] Example 2

[0053] 1 to 3 and 6 to 7 , a second embodiment of the present invention is provided, which provides a high-temperature gas-cooled reactor bypass seal inspection device, comprising a reactor unit 100 , a protective layer 101 , and a plurality of graphite blocks 102 disposed within the protective layer 101 ;

[0054] The sealing unit 200 includes a longitudinal sealing member 201 and a transverse sealing rack 202 provided on one side of the longitudinal sealing member 201;

[0055] The adjustment unit 300 includes a plurality of rotating rods 301 , a transmission member 302 disposed on one side of the rotating rods 301 , and a limiting cover 303 disposed on one side of the transmission member 302 .

[0056] The graphite block 102 includes a bypass channel 102a and a trapezoidal protrusion 102b disposed on one side of the graphite block 102;

[0057] The cross-sectional shape of the longitudinal sealing member 201 is consistent with the gap formed between two adjacent graphite blocks 102 on the same plane;

[0058] The longitudinal sealing member 201 includes a first inserting groove 201 a longitudinally disposed therein, and a second inserting groove 201 b transversely disposed therein.

[0059] It should be noted that the protective layer 101 is made of a high-strength and high-density metal material, specifically steel or lead, which protects the reactor to prevent the graphite block 102 from direct contact with the external environment, reducing oxidation and corrosion of the graphite block 102. It also plays a role in sealing radioactive substances to prevent leakage, as well as supporting and improving stability. The cross-section of the graphite block 102 is a fan ring shape. The graphite block is divided into two layers, and each layer is surrounded by 12 graphite blocks 102. After being surrounded, the graphite blocks 102 are arranged in a circular ring shape in the protective layer 101.

[0060] Preferably, the sealing unit 200 is composed of a longitudinal sealing member 201 and a transverse sealing rack 202 to seal the gap between every two adjacent graphite blocks 102, that is, to control the structural bypass flow of the helium coolant in the graphite gap.

[0061] Preferably, the graphite block 102 has a bypass channel 102a extending longitudinally along its center. The bypass channel 102a is a bypass channel for circulating helium coolant. The sealing performance of this part is mainly simulated and tested by this device. A trapezoidal protrusion 102b is fixedly connected to one side of the graphite block 102, and the two are fixed as an integral structure. This will form a through sealing area between the two adjacent graphite blocks 102, which is divided into a longitudinal through area and a transverse through area. The longitudinal seal 201 is inserted into this longitudinal through area. The cross section of the longitudinal seal 201 fits the inner wall of this area. After insertion, the longitudinal gap can be sealed. The longitudinal seal 201 also includes a first insertion groove 201a extending longitudinally through the center of its upper surface, and a second transverse insertion groove 201b extending longitudinally in the middle thereof. The second insertion groove 201b is in the shape of a curved 1 / 24 circular ring, facing the transverse gap between the upper and lower graphite blocks 102.

[0062] Preferably, the transverse sealing rack 202 is an arc-shaped 1 / 24 annular rack, which is movably arranged in the second plug-in groove 201b. The transverse sealing rack 202 is used to seal the gap between the upper and lower graphite blocks 102. When the longitudinal seal 201 is inserted and aligned, the rotating rod 301 inserted therein is rotated. Since the gear 301e fixedly connected to the outer wall of the rotating rod 301 is engaged with the transverse sealing rack 202, the rotating rod 301 will drive the transverse sealing rack 202 to rotate along the second plug-in groove 201b to transfer the transverse sealing rack 202 into the transverse gap not sealed by the longitudinal seal 201, thereby achieving complete sealing of the transverse gap.

[0063] Example 3

[0064] 1 to 7 , a third embodiment of the present invention includes the above embodiments, and differs from the above embodiments in that: the first insertion slot 201a further includes a first insertion slot 201a having an upper half whose aperture gradually decreases from top to bottom, a spiral groove 201a-1 provided on an inner wall thereof, and an annular groove 201a-2 provided below the spiral groove 201a-1;

[0065] The protective layer 101 includes a mounting groove 101a provided at the bottom thereof;

[0066] The mounting groove 101 a includes a compression spring 101 a - 1 disposed therein, and a plurality of fixed guide balls 101 a - 2 disposed on the inner wall of the mounting groove 101 a .

[0067] The rotating rod 301 includes a pressing knob 301a, a pressing spring 301b arranged on one side of the pressing knob 301a, a first insertion rod 301c arranged on one side of the pressing spring 301b, a second insertion rod 301d arranged on one side of the first insertion rod 301c, a gear 301e arranged on the outer wall of the second insertion rod 301d, and a clamp 301f arranged on one side of the second insertion rod 301d.

[0068] The diameter of the first insertion rod 301c gradually decreases from top to bottom. The first insertion rod 301c further includes a spherical protrusion 301c-1 provided on its outer wall.

[0069] The transmission member 302 includes a disc gear 302a, a connecting rod 302b disposed on one side of the disc gear 302a, and a rotating rod 302c disposed on one side of the connecting rod 302b.

[0070] The limiting cover 303 includes a plurality of limiting protrusions 303a provided on one side thereof.

[0071] It should be noted that the pressing knob 301a is disc-shaped, and has longitudinal teeth around it. The pressing knob 301a is fixedly connected to the first plug rod 301c through a short rod, and a pressing spring 301b is surrounded by the short rod to buffer the pressing knob 301a. The first plug rod 301c and the second plug rod 301d are fixedly connected to form a whole. The outer wall of the second plug rod 301d is fixedly connected to a gear 301e, and the clamp 301f is fixedly connected to the other side of the second plug rod 301d.

[0072] Preferably, the diameter of the first rod 301c gradually decreases from top to bottom until the diameter is consistent with the second rod 301d, and the upper rod diameter is about 1.5 times the lower rod diameter. A fixed spherical protrusion 301c-1 is provided on one side of the surface of the first rod 301c close to the gear 301e. The clamping head 301f is fixedly connected to the end of the second insertion rod 301d. The clamping head 301f is an irregular raised spherical shape. A spiral annular groove is opened along the outer wall of the sphere of the clamping head 301f. This groove is engaged with the fixed guide ball 101a-2 fixedly connected to the inner wall of the mounting groove 101a. Due to this shape, it can be inserted into the mounting groove 101a by rotating the rotating rod 301, and when it is rotated into the mounting groove 101a, it can continue to rotate without being affected. Once reversed, it will drive the rotating rod 301 to move out of the mounting groove 101a. This structure is very suitable for scenarios where the rotating rod 301 still needs to be rotated to drive the transverse sealing rack 202 after the insertion is completed.

[0073] Preferably, the longitudinal first insertion groove 201a is divided into an upper half and a lower half along the horizontal gap between the upper and lower graphite blocks 102, wherein the aperture of the upper half gradually decreases from top to bottom, and the upper aperture is about 1.5 times the lower aperture, slightly larger than the diameter of the first insertion rod 301c. The inner wall of the upper half of the first insertion groove 201a is also provided with a spiral groove 201a-1, and the spiral groove 201a-1 is also provided with smooth rounded corners from top to bottom. An annular groove 201a-2 is also provided below the spiral groove 201a-1, and the annular groove 201a-2 is connected to the spiral groove 201a-1 through a longitudinal groove. When we insert the rotating rod 301 into the first insertion groove 201a, the spherical protrusion 301c-1 fixedly connected to the outer wall of the rotating rod 301 gradually aligns with the spiral groove 2 01a-1 is engaged, and its direction is adjusted to be fixed in the direction of the spiral groove 201a-1 and slides into the annular groove 201a-2 after reaching the end of the spiral groove 201a-1, and is limited in the annular groove 201a-2. Since it is inserted and the position of the gear 301e and the transverse sealing rack 202 is always at the bottom position of the spiral groove 201a-1, it can well avoid the collision between the two parts of the teeth and prevent the problem of the rotating rod 301 being stuck due to the jamming between the teeth.

[0074] When the locking cam 303 is pressed, the locking cam 303 is pressed against the locking cam 301, and the locking cam 303 is tightened to lock the locking cam 301.

[0075] Usage steps: 1. Simulate a high-temperature gas-cooled reactor and stack the graphite blocks 102 in two layers in a circular shape within the protective layer 101;

[0076] 2. Place the transverse sealing rack 202 into the second insertion groove 201b of the longitudinal sealing member 201;

[0077] 3. Insert the longitudinal seal 201 along the longitudinal through area between the graphite blocks 102 to seal the longitudinal gap between two adjacent graphite blocks 102;

[0078] 4. Insert the transfer rods 301 of the adjustment unit 300 into the first insertion slots on the longitudinal seal 201 one by one. At this time, the upper limit protrusion 303a of the limit cover 303 just engages with the upper recess of the trapezoidal protrusion 102b of the upper graphite block 102;

[0079] 5. Press the limit cover 303 evenly from the top of the device. During the pressing process, the spherical protrusion 301c-1 on the rotating rod 301 will gradually engage with the spiral groove 201a. Adjust the direction so that the spherical protrusion 301c-1 slides into the annular groove 201a-2 after reaching the end of the spiral groove 201a-1 and is retained in the annular groove 201a-2. At the same time, the gear 301e will gradually engage with the transverse sealing rack 202. At the same time, the clamp 301f at the end of the rotating rod 301 will gradually engage with the fixed guide ball 101a-2 and insert into the installation groove 101a.

[0080] 6. Rotate the rotating rod 302c to synchronize the disc-mounted gear 302a with the pressing knob on the rotating rod 301. The gear 301e engages with the transverse sealing rack 202, driving the rack to extend against the wall of the graphite block 102, thereby sealing the gap between the upper and lower graphite blocks 102.

[0081] 7. Normal temperature and normal pressure air or high temperature and high pressure helium is injected as the flow medium into one side of the bypass passage 102a, and the gas is drawn out through the outlet on the other side of the bypass passage 102a and recovered. The remaining unrecovered leaked gas is extracted from the other side of the bypass passage 102a by a blower, and the measured bypass flow rate is compared with the upper limit of leakage considered in the reactor design to verify the bypass control effect.

[0082] In summary, the present invention blocks longitudinal bypass and lateral leakage of helium coolant through the sealing unit 200. This simulation test device can simulate the operation of a high-temperature gas-cooled reactor (HTGR), saving costs and reducing safety hazards. The data generated by the simulation can effectively support the design and demonstration of the HTGR reactor structure, further improving the safety and reliability of the pebble-bed HTGR.

[0083] It is important to note that the construction and arrangement of the present application shown in a number of different exemplary embodiments are merely illustrative. Although only a few embodiments are described in detail in this disclosure, it should be readily understood by those who refer to this disclosure that many modifications are possible (e.g., the size, scale, structure, shape and proportion of various elements, as well as parameter values ​​(e.g., temperature, pressure, etc.), mounting arrangements, use of materials, color, directional changes, etc.) without departing substantially from the novel teachings and advantages of the subject matter described in this application. For example, an element shown as integrally formed may be composed of multiple parts or elements, the position of the element may be inverted or otherwise changed, and the nature or number or position of the discrete elements may be altered or changed. Therefore, all such modifications are intended to be included within the scope of the present invention. The order or sequence of any process or method steps may be changed or reordered according to alternative embodiments. In the claims, any "means plus function" clause is intended to cover the structure described herein that performs the function, and is not only structurally equivalent but also equivalent structures. Other replacements, modifications, changes, and omissions may be made in the design, operating conditions, and arrangement of the exemplary embodiments without departing from the scope of the present invention. Therefore, the invention is not limited to the specific embodiments, but extends to various modifications that still fall within the scope of the appended claims.

[0084] Additionally, in order to provide a concise description of exemplary embodiments, all features of an actual embodiment (i.e., those features that are not relevant to the best mode presently contemplated for carrying out the invention or those that are not relevant to implementing the invention) may not be described.

[0085] It will be appreciated that in the development of any actual embodiment, as in any engineering or design project, numerous implementation-specific decisions may be made. Such a development effort may be complex and time-consuming, but will, for those of ordinary skill having the benefit of this disclosure, be a routine undertaking of design, fabrication, and production without undue experimentation.

[0086] It should be noted that the above embodiments are only used to illustrate the technical solutions of the present invention and are not intended to limit the present invention. Although the present invention has been described in detail with reference to the preferred embodiments, those skilled in the art should understand that the technical solutions of the present invention may be modified or replaced by equivalents without departing from the spirit and scope of the technical solutions of the present invention, which should all be included in the scope of the claims of the present invention.

Claims

1. A method for controlling coolant bypass flow in a high temperature gas-cooled reactor, characterized in that: The steps include: Identify structural bypass locations within the reactor; Construct a dovetail groove structure sealing key to seal the bypass channel; The side flow sealing performance test is carried out on the processing simulation body to verify the side flow control effect.

2. A high temperature gas-cooled reactor coolant bypass flow control method according to claim 1, characterized in that: The identification of structural bypass flow in the reactor is specifically to analyze the narrow gap bypass flow that affects the temperature distribution of the pebble bed according to the structural characteristics of the reactor, and to quantitatively analyze the size of the bypass flow and the influence on the flow and heat transfer in the pebble bed through thermal hydraulic calculations, so as to confirm the main narrow gap bypass flow.

3. A high temperature gas-cooled reactor coolant bypass flow control method according to claim 2, characterized in that: Specifically, the dovetail groove structure sealing key is designed on the ball bed side of the identified narrow gap, the transverse sealing key of the upper surface narrow gap between the sealed graphite blocks and the vertical sealing key of the vertical narrow gap between the sealed graphite blocks that penetrates the entire side reflection layer, thereby blocking the lateral bypass flow and longitudinal leakage flow of the helium coolant.

4. The high temperature gas-cooled reactor bypass leak tightness test device according to claim 3, characterized in that: A high temperature gas-cooled reactor bypass leak tightness test device, characterized in that it includes: A reactor unit (100) comprises a protective layer (101) and a plurality of groups of graphite blocks (102) arranged in the protective layer (101); A sealing unit (200) comprising a longitudinal sealing member (201) and a transverse sealing rack (202) arranged on one side of the longitudinal sealing member (201); The adjustment unit (300) comprises a plurality of rotating rods (301), a transmission member (302) arranged on one side of the rotating rods (301), and a limit cover (303) arranged on one side of the transmission member (302).

5. The high temperature gas-cooled reactor bypass leak tightness test device according to claim 4, characterized in that: The protective layer (101) comprises a mounting groove (101a) arranged at the bottom thereof; The installation groove (101a) comprises a compression spring (101a-1) arranged inside the installation groove, and a plurality of fixed guide balls (101a-2) arranged on the inner wall of the installation groove (101a).

6. The high temperature gas-cooled reactor bypass leak tightness test device according to claim 5, characterized in that: The graphite block (102) comprises a bypass channel (102a) and a trapezoidal protrusion (102b) arranged on one side of the graphite block (102).

7. The high temperature gas-cooled reactor bypass leak tightness test device according to claim 6, characterized in that: The cross-sectional shape of the longitudinal sealing member (201) is consistent with the gap formed between two adjacent graphite blocks (102) on the same plane; The longitudinal sealing member (201) comprises a first plug-in groove (201a) longitudinally arranged inside the longitudinal sealing member (201), and a second plug-in groove (201b) transversely arranged inside the longitudinal sealing member (201); The aperture of the upper half of the first plugging groove (201a) gradually decreases from top to bottom, and the first plugging groove (201a) further comprises a spiral groove (201a-1) arranged on its inner wall, and an annular groove (201a-2) arranged below the spiral groove (201a-1) and in communication.

8. The high temperature gas-cooled reactor bypass leak tightness test device according to claim 7, characterized in that: The rotating rod (301) comprises a pressing knob (301a), a pressing spring (301b) arranged on one side of the pressing knob (301a), a first plug rod (301c) arranged on one side of the pressing spring (301b), a second plug rod (301d) arranged on one side of the first plug rod (301c), a gear (301e) arranged on the outer wall of the second plug rod (301d), and a clamp (301f) arranged on one side of the second plug rod (301d); The diameter of the first insertion rod (301c) gradually decreases from top to bottom, and the first insertion rod (301c) further comprises a spherical protrusion (301c-1) arranged on its outer wall.

9. The high temperature gas-cooled reactor bypass leak tightness test device according to claim 8, characterized in that: The transmission member (302) comprises a disc-shaped gear (302a), a connecting rod (302b) arranged on one side of the disc-shaped gear (302a), and a rotating rod (302c) arranged on one side of the connecting rod (302b).

10. The high temperature gas-cooled reactor bypass leak tightness test device according to claim 9, characterized in that: The limiting cover (303) comprises a plurality of limiting protrusions (303a) arranged on one side thereof.

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