Support structure for a reactor and method of manufacturing the support structure

By designing a support structure with a diameter greater than the first accommodation part and determining the maximum stress of the support structure according to the Tresca yield criterion, the problem of insufficient equipment support strength of the nuclear reactor under earthquake is solved, and the safety and repair difficulty of the reactor are improved .

CN113990531BActive Publication Date: 2025-01-14CHINA INSTITUTE OF ATOMIC ENERGY
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Patent Information

Application Number
CN202111230162.0
Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
Filing Date
2021-10-22
Publication Date
2025-01-14
Estimated Expiration
2041-10-22

AI Technical Summary

Technical Problem

The safety of nuclear reactors during earthquakes is difficult to ensure, the existing support structure is difficult to repair after earthquakes, and the equipment support strength is not enough to cope with seismic loads.

Method used

A support structure is designed, wherein the diameter of the second receiving part is larger than the first receiving part, and the maximum stress and diameter relationship of the support structure under seismic conditions is determined through the Tresca yield criteria to ensure that the stress that the support structure can withstand during earthquakes is not low. To improve the bearing strength.

Benefits of technology

It improves the reliable operation capability of the equipment in the reactor under seismic load, enhances the safety and repair difficulty of the reactor, and ensures the stable operation of the nuclear reactor under seismic conditions.

✦ Generated by Eureka AI based on patent content.

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Abstract

The embodiment of the present invention discloses a support structure for a reactor and a method for manufacturing the support structure, the support structure comprising: a first accommodating portion; a second accommodating portion, the second accommodating portion being connected to the first accommodating portion, the first accommodating portion and the second accommodating portion being used to accommodate equipment in the reactor, and the coolant in the reactor is in contact with the equipment through the first accommodating portion and / or the second accommodating portion; wherein the diameter of the second accommodating portion is set to be larger than the diameter of the first accommodating portion to improve the strength of the first accommodating portion and / or the second accommodating portion. The support structure has high strength, so that the support structure can reliably support the equipment in the reactor under seismic loads.
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Description

Technical Field

[0001] The invention relates to the technical field of nuclear reactors, and in particular to a supporting structure for a reactor and a method for manufacturing the supporting structure. Background Art

[0002] Nuclear power structure is a major project of national energy strategy, with high construction cost. Once damaged by earthquake, it will lead to economic losses and difficult to repair after the earthquake. my country is a country with many earthquakes, and ensuring the safety of nuclear reactors under earthquakes is a key issue. The equipment supports in the reactor are set on the supports inside the reactor, which requires that the supports of the equipment in the reactor have sufficient support strength so that the equipment in the reactor can still operate reliably under earthquake loads. Summary of the invention

[0003] In view of the above problems, the present invention is proposed to provide a support structure for a reactor and a method for manufacturing the support structure that overcomes the above problems or at least partially solves the above problems.

[0004] A first aspect of an embodiment of the present invention provides a support structure for a reactor, comprising: a first accommodating portion; a second accommodating portion, wherein the second accommodating portion is connected to the first accommodating portion, the first accommodating portion and the second accommodating portion are used to accommodate equipment in the reactor, and the coolant in the reactor is in contact with the equipment through the first accommodating portion and / or the second accommodating portion; wherein the diameter of the second accommodating portion is set to be larger than the diameter of the first accommodating portion to increase the strength of the first accommodating portion and / or the second accommodating portion.

[0005] A second aspect of an embodiment of the present invention provides a method for manufacturing a support structure for a reactor, the method being used to manufacture the support structure provided by the first aspect of an embodiment of the present invention, comprising: characterizing the relationship between the stress borne by the second housing portion under seismic conditions and the diameter of the second housing portion; determining the maximum stress that the second housing portion can withstand based on the Tresca yield criterion; determining the diameter of the second housing portion based on the relationship between the stress borne by the second housing portion under seismic conditions and the diameter of the second housing portion, and the maximum stress that the second housing portion can withstand, wherein the diameter makes the stress borne by the second housing portion under seismic conditions less than or equal to the maximum stress that the second housing portion can withstand; and manufacturing the support structure based on the diameter of the second housing portion.

[0006] The third aspect of the embodiments of the present invention provides a reactor, comprising: the support structure for the reactor provided by the first aspect of the embodiments of the present invention; a heat exchanger, the heat exchanger is fixed to the support structure; or a power pump, the power pump is fixed to the support structure. BRIEF DESCRIPTION OF THE DRAWINGS

[0007] Other objects and advantages of the present invention will become apparent from the following description of the present invention with reference to the accompanying drawings, which will help to provide a comprehensive understanding of the present invention.

[0008] Figure 1 is a schematic structural diagram of a support structure for a reactor provided according to one embodiment of the present invention;

[0009] Figure 2 is based on Figure 1 A schematic diagram of the arrangement of the transition portion 30 of the support structure for the reactor is provided;

[0010] Figure 3 It is a schematic structural diagram of a fixing part and a compensating part of a supporting structure for a reactor provided by one embodiment of the present invention.

[0011] In the drawings, 10 is a first accommodating portion, 11 is a connecting portion, 20 is a second accommodating portion, 30 is a transition portion, 40 is a sealing portion, 50 is a compensating portion, and 60 is a fixing portion.

[0012] It should be noted that the drawings are not drawn to scale, and for illustrative purposes, elements of similar structure or function are generally represented by similar reference numerals throughout the drawings. It should also be noted that the drawings are only for the convenience of describing the preferred embodiments, not the invention itself. The drawings do not illustrate every aspect of the described embodiments, and do not limit the scope of the invention. DETAILED DESCRIPTION

[0013] In order to make the purpose, technical solution and advantages of the present invention clearer, the technical solution of the present invention will be clearly and completely described below in conjunction with the accompanying drawings of the embodiments of the present invention. Obviously, the described embodiment is one embodiment of the present invention, not all embodiments. Based on the described embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0014] Unless otherwise defined, technical or scientific terms used in the present invention shall have the common meanings understood by one having ordinary skills in the field to which the present invention belongs.

[0015] Since my country is a country prone to earthquakes, especially since the China Demonstration Fast Reactor is located at a location with an earthquake intensity of 9, it is necessary to ensure the safety of the nuclear reactor under earthquakes. The supporting structure in the reactor plays the role of supporting the equipment in the reactor. It is necessary to improve the supporting strength of the supporting structure so that the equipment in the reactor can operate reliably under earthquake loads, thereby ensuring the safe operation or safe shutdown of the reactor.

[0016] One embodiment of the present invention provides a support structure for a reactor. Figure 1 is a schematic structural diagram of a support structure for a reactor provided according to an embodiment of the present invention, see Figure 1 , the supporting structure comprises:

[0017] A first receiving portion 10;

[0018] The second accommodating portion 20 is connected to the first accommodating portion 10. The first accommodating portion 10 and the second accommodating portion 20 are used to accommodate the equipment in the reactor. In an embodiment of the present invention, the first accommodating portion 10 can be covered with the equipment in the reactor to protect the equipment in the reactor. In other embodiments, the second accommodating portion 20 can also be covered with the equipment in the reactor. Optionally, both the first accommodating portion 10 and the second accommodating portion 20 can be cylinders. In some embodiments, the first accommodating portion 10 can be used to accommodate the equipment in the reactor, and the second accommodating portion 20 can be used to support the equipment in the reactor and the first accommodating portion 10.

[0019] The coolant in the reactor is brought into contact with the equipment through the first accommodation portion 10 and / or the second accommodation portion 20; optionally, the equipment in the reactor may be a heat exchanger, and the coolant in the reactor is brought into the first accommodation portion 10 and / or the second accommodation portion 20 through the first accommodation portion 10 and / or the second accommodation portion 20, so that the coolant is cooled by heat exchange through the heat exchanger; the equipment in the reactor may also be a power pump, and the coolant in the reactor is brought into the first accommodation portion 10 and / or the second accommodation portion 20 through the first accommodation portion 10 and / or the second accommodation portion 20, so that the power pump pushes the coolant to be transferred into the reactor.

[0020] The heat exchanger is a heat exchange device inside the reactor. It can be used to exchange heat with the coolant, conduct heat, and work with other equipment in the reactor to discharge the heat from the core.

[0021] Heat exchangers can include independent heat exchangers, intermediate heat exchangers and air heat exchangers, etc.

[0022] Independent heat exchangers and air heat exchangers can be equipment within the passive residual heat removal system. The passive residual heat removal system is a safety system for the reactor. It does not require the drive of a pump, but relies on natural circulation force to continuously remove the heat from the core in accidents such as power outages in the entire plant that may cause the loss of the three-circuit heat sink, thereby ensuring the safe shutdown of the fast reactor system. During the operation of the passive residual heat removal system, the natural circulation of one circuit brings the core heat into the independent heat exchanger, and the heat is transferred to the intermediate circuit through the independent heat exchanger. The coolant in the intermediate circuit carries the heat into the air heat exchanger and transfers it to the air in the exhaust chimney. The natural circulation brings the heat into the atmosphere, thereby achieving safe discharge of the core heat.

[0023] The intermediate heat exchanger is connected to the primary circuit and the secondary circuit of the reactor, and the core heat derived from the primary circuit is transferred to the secondary circuit through the intermediate heat exchanger.

[0024] The primary cooling system in the reactor plays the role of discharging the heat generated by the core, and the coolant transmission structure plays the role of transmitting the coolant in the primary cooling system. Specifically, the coolant transmission structure transmits the coolant from the power pump to the reactor core. When the coolant in the primary cooling system passes through the core, the fission energy generated in the fuel elements of the core is discharged from the core, maintaining the normal working conditions of the core and ensuring the safe operation of the reactor. The power pump provides power for transmitting the coolant. Optionally, the power pump can be a centrifugal pump. When the pump is full of coolant, the impeller rotates to generate centrifugal force. The coolant in the impeller channel is thrown to the periphery and flows into the pump casing under the action of centrifugal force. At this time, the pressure at the center of the impeller is reduced, and the pressure is lower than the pressure in the tube. The coolant flows into the impeller under the action of the pressure difference, so that the centrifugal pump can continuously inhale the coolant, thereby completing the circulation of the coolant.

[0025] Optionally, the reactor here can be a pool-type fast reactor, specifically, the reactor can be a China Demonstration Fast Reactor, or can be other types of reactors; the coolant can be liquid sodium or liquid lead-bismuth alloy, etc.

[0026] Among them, the diameter of the second accommodating part 20 is set to be larger than the diameter of the first accommodating part 10, so as to improve the strength of the first accommodating part 10 and / or the second accommodating part 20, and can also prevent the equipment in the reactor from colliding with the second accommodating part 20 when shaking, thereby affecting the safe operation of the equipment in the reactor.

[0027] The supporting structure for a reactor provided by an embodiment of the present invention further includes:

[0028] Transition section 30, Figure 2 is based on Figure 1 A schematic diagram of the arrangement of the transition portion 30 of the support structure provided for the reactor is shown in Figure 2 , the transition portion 30 is connected to the bottom end of the first accommodating portion 10 and the top end of the second accommodating portion 20, wherein the bottom end of the first accommodating portion 10 is arranged at a predetermined position above the top end of the second accommodating portion 20. In other embodiments, the bottom end of the first accommodating portion 10 may also be arranged at the same height as the top end of the second accommodating portion 20. The transition portion 30 may be used to accommodate the diameter change between the first accommodating portion 10 and the second accommodating portion 20. In some embodiments, the first accommodating portion 10 and the second accommodating portion 20 may be integrally formed. In other embodiments, the first accommodating portion 10 and the second accommodating portion 20 may also be manufactured separately to facilitate on-site installation.

[0029] In an embodiment of the present invention, the support structure may further include a connection portion (not shown in the figure) for connecting the first accommodating portion 10 and the second accommodating portion 20. In an embodiment of the present invention, the connection portion may include a first flange and a second flange, the first flange connecting the first accommodating portion 10, the second flange connecting the second accommodating portion 20, and the first accommodating portion 10 and the second accommodating portion 20 are connected by connecting the first flange and the second flange. In other embodiments, the connection portion may also be a thread, and the first accommodating portion 10 and the second accommodating portion 20 may be connected by a thread. In some embodiments, according to different actual needs, the first accommodating portion 10 and the second accommodating portion 20 may also be connected by welding connection, socket connection, pipe bonding connection, etc. The above-mentioned pipe connection method should be known to those skilled in the art and will not be repeated here.

[0030] Optionally, the support structure may further include a shock absorbing portion (not shown in the figure), which is arranged between the first accommodating portion 10 and the second accommodating portion 20 through a connecting portion. The connecting portion may be provided with a groove, and the shock absorbing portion can slide in the groove to provide shock absorption and buffering for the equipment in the reactor.

[0031] In an embodiment of the present invention, the support structure further comprises:

[0032] The sealing portion 40 is disposed at the connection between the first accommodating portion 10 and the second accommodating portion 20, and is used to prevent the coolant in the first accommodating portion 10 and / or the second accommodating portion 20 from flowing out from the connection and affecting the equipment outside the first accommodating portion 10 and the second accommodating portion 20, and to improve the sealing performance of the first accommodating portion 10 and the second accommodating portion 20, and can also be used to shield the influence of the coolant outside the first accommodating portion 10 and the second accommodating portion 20.

[0033] In the embodiment of the present invention, the sealing portion 40 can be arranged outside the first accommodating portion 10, or outside the second accommodating portion 20. Optionally, the sealing portion 40 can also be arranged inside the first accommodating portion 10 and / or the second accommodating portion 20 to improve the sealing effect, reduce the influence, and enhance the sealing performance of the first accommodating portion 10 and the second accommodating portion 20.

[0034] In the embodiment of the present invention, the first accommodation portion 10 is provided with a connecting portion 11, and the connecting portion 11 is used to allow the coolant in the reactor to flow into and / or out of the first accommodation portion 10. Optionally, the connecting portion 11 may be circumferentially arranged on the first accommodation portion 10.

[0035] Optionally, the first accommodating portion 10 may be provided with a plurality of connecting portions 11 to make the circulation efficiency of the coolant in the reactor higher. In an embodiment of the present invention, the connecting portion 11 disposed at the top may be used to allow the coolant to flow into the first accommodating portion 10, and the connecting portion 11 disposed at the bottom may be used to allow the coolant to flow out of the first accommodating portion 10. In other embodiments, the connecting portion 11 disposed at the top may be used to allow the coolant to flow out of the first accommodating portion 10, and the connecting portion 11 disposed at the bottom may be used to allow the coolant to flow into the first accommodating portion 10.

[0036] In some embodiments, the second accommodation portion 20 may also be provided with a connecting portion 11 , and those skilled in the art may set the number and position of the connecting portion 11 according to actual needs.

[0037] Optionally, the bottom of the first accommodating part 10 and / or the second accommodating part 20 may not be sealed, and the coolant may flow in and / or out through the bottom of the first accommodating part 10 and / or the second accommodating part 20; the bottom of the first accommodating part 10 and / or the second accommodating part 20 may also be sealed by a seal (not shown in the figure), which improves the sealing performance of the first accommodating part 10 and / or the second accommodating part 20 and protects the equipment in the reactor. A connecting portion may be provided on the seal to allow the coolant to flow in and / or out through the seal.

[0038] In an embodiment of the present invention, the connecting portion 11 may include a plurality of through holes, and the plurality of through holes are evenly arranged in the first accommodating portion 10, which can increase the speed at which the coolant flows into and / or flows out of the first accommodating portion 10. In an embodiment of the present invention, the sizes of the plurality of through holes may be consistent. In other embodiments, the sizes of the plurality of through holes may be inconsistent, so as to make the speed at which the coolant flows through the through holes different, thereby increasing the flow rate of the coolant. In an embodiment of the present invention, the shape of the through hole may be circular, and in other embodiments, those skilled in the art may set the through hole to a different shape according to the actual needs.

[0039] In an embodiment of the present invention, a scale-shaped cover may be provided on the through hole, so that the coolant can flow into or out of the through hole in one direction. Specifically, the scale-shaped cover may be provided on the inner side of the first accommodating portion 10, so as to allow the coolant to flow into the first accommodating portion 10 from outside the first accommodating portion 10 in one direction; or, the scale-shaped cover may be provided on the outer side of the first accommodating portion 10, so as to allow the coolant to flow into the first accommodating portion 10 from inside the first accommodating portion 10 in one direction, thereby improving the circulation efficiency of the coolant. In other embodiments, those skilled in the art may set the position of the cover and the connecting portion 11 according to the actual flow direction of the coolant.

[0040] Figure 3 is a schematic structural diagram of a fixing part and a compensating part of a supporting structure for a reactor provided by an embodiment of the present invention, see Figure 3In an embodiment of the present invention, the support structure may further include a compensating portion 50, which may be disposed in the first accommodating portion 10 or in the second accommodating portion 20, for compensating for the axial deformation of the first accommodating portion 10 and the second accommodating portion 20. Optionally, the compensating portion 50 may be a C-shaped expansion joint. In other embodiments, the compensating portion 50 may also be a U-shaped expansion joint or a bellows expansion joint. Those skilled in the art may select a compensating portion of a suitable shape or type according to the needs of the actual situation and the ease of installation.

[0041] In an embodiment of the present invention, the support structure may further include a fixing portion 60, which may be disposed on the top of the first accommodating portion 10, and fixed to the reactor. Those skilled in the art may understand that a reactor vessel refers to a closed container that houses a reactor and withstands its huge operating pressure, also known as a reactor pressure vessel, and optionally, the fixing portion 60 may be connected to the reactor vessel, specifically, may be welded to a conical top cover of the reactor vessel.

[0042] In an embodiment of the present invention, the support structure may further include a measuring part (not shown in the figure), which may be arranged in the first accommodating part 10 or in the second accommodating part 20. In an embodiment of the present invention, the measuring part may be a thermocouple, which is used to measure the temperature of the coolant flowing into and / or out of the first accommodating part 10 and / or the second accommodating part 20, and may also be used to measure the temperature of the coolant in the first accommodating part 10 and the second accommodating part 20, so as to monitor the temperature of the coolant circulating in the reactor in real time. In other embodiments, the measuring part may also be a flow meter, which is used to measure the flow rate of the coolant flowing into and / or out of the first accommodating part 10 and / or the second accommodating part 20, and monitor the flow rate data of the coolant in real time. Through the flow data, it is possible to determine whether the reactor is operating normally, understand the operating status of the reactor in real time, and enable the reactor to operate safely.

[0043] Those skilled in the art will appreciate that the equipment within the reactor may include a power pump and a heat exchanger.

[0044] An embodiment of the present invention provides a method for manufacturing a support structure for a reactor. The manufacturing method is used to manufacture the support structure for a reactor provided by an embodiment of the present invention. The equipment in the reactor is arranged on the support structure through a connecting portion. Optionally, the connecting portion may be a connecting pipe. For example, a power pump in the reactor is arranged on the support structure through the connecting portion. The method includes:

[0045] Characterize the relationship between the stress borne by the second accommodation portion 20 under earthquake conditions and the diameter of the second accommodation portion 20;

[0046] According to the Tresca yield criterion, the maximum stress that the second receiving portion 20 can withstand is determined; the Tresca yield criterion states that when the maximum shear stress reaches a certain value inherent in the material, the material enters the plastic deformation stage, and the constant value depends on the properties of the material under deformation conditions and has nothing to do with the stress state. In other words, according to the Tresca yield criterion and the properties of the materials of the first receiving portion 10 and / or the second receiving portion 20 under deformation conditions, the maximum stress that the second receiving portion 20 can withstand is determined.

[0047] The diameter of the second accommodation portion 20 is determined according to the relationship between the stress borne by the second accommodation portion 20 under earthquake conditions and the diameter of the second accommodation portion 20, and the maximum stress that the second accommodation portion 20 can withstand.

[0048] The diameter is such that the stress borne by the second accommodation portion 20 under earthquake conditions is less than or equal to the maximum stress that the second accommodation portion 20 can withstand;

[0049] The support structure is produced according to the diameter of the second receptacle 20 .

[0050] Optionally, the stress that the second accommodating portion 20 is subjected to under an earthquake condition may be the stress that the bottom of the second accommodating portion 20 is subjected to under an earthquake condition.

[0051] In an embodiment of the present invention, the relationship between the stress borne by the second accommodation portion 20 under earthquake conditions and the diameter of the second accommodation portion 20 is characterized, including:

[0052] Determine the stress borne by the second accommodation portion 20 under earthquake conditions according to the first principal stress and the third principal stress borne by the second accommodation portion 20, wherein the first principal stress is greater than or equal to the third principal stress;

[0053] According to the stress borne by the second accommodation portion 20 under the earthquake condition, the relationship between the stress borne by the second accommodation portion 20 under the earthquake condition and the diameter of the second accommodation portion 20 is determined.

[0054] σ s =σ1-σ3 (1)

[0055] In formula (1), σ s is the maximum stress that the second accommodation portion 20 can withstand, σ1 is the first principal stress that the second accommodation portion 20 can withstand under earthquake conditions, and σ3 is the third principal stress that the second accommodation portion 20 can withstand under earthquake conditions.

[0056] Those skilled in the art can understand that for the stress state borne by the second accommodating portion 20, a rectangular coordinate system (x, y, z) can be taken so that the three coordinate axes coincide with the three principal stress directions that are perpendicular to each other. The three principal stresses are arranged in order from large to small, namely the first principal stress, the second principal stress and the third principal stress.

[0057] In an embodiment of the present invention, the method further comprises:

[0058] According to the axial stress and the shear stress received by the second accommodation portion 20 , the first principal stress and the third principal stress received by the second accommodation portion 20 are determined.

[0059] Specifically, the first principal stress can be expressed by the following formula (2), and the third principal stress can be expressed by the following formula (3).

[0060]

[0061]

[0062] In formula (2) and formula (3), σ x is the axial stress of the second receiving portion 20 on the X-axis, σ y is the stress of the second receiving portion 20 on the y-axis, and τ is the shear stress exerted on the second receiving portion 20 .

[0063] In the embodiment of the present invention, the axial stress on the second accommodation portion 20 is determined by the following steps:

[0064] Determine respectively the seismic load, the gravity load and the axial stress of the connecting portion on the second accommodation portion 20;

[0065] The axial stress on the second receiving portion 20 is determined according to the earthquake load, the gravity load and the axial stress of the connecting portion on the second receiving portion 20 .

[0066] Optionally, determining the axial stress on the second accommodation portion further includes:

[0067] The axial stress of the transition portion 30 on the second receiving portion 20 is determined.

[0068] σ x =σ i +σ g +σ p (4)

[0069] In the above formula (4), σ i is the axial stress of the second accommodation part 20 caused by the earthquake load, σ g is the axial stress of the gravity load on the second receiving portion 20, σ pis the axial stress of the connecting portion and / or transition portion 30 on the second receiving portion 20. Optionally, σ p It may be the axial stress of the pipe load on the bottom of the second accommodation portion 20 .

[0070] Specifically, the axial stress of the second accommodation portion 20 caused by the earthquake load is calculated by the following formula (5).

[0071]

[0072] In the above formula (5), F vi is the resultant vertical inertial force of the seismic load on the second accommodation portion 20, A is the cross-sectional area of ​​the second accommodation portion 20, M hi is the bending moment of the seismic load on the second accommodation part 20, r o is the outer radius of the cross section of the second accommodation portion 20 , and I is the cross-sectional moment of inertia of the second accommodation portion 20 .

[0073] in,

[0074]

[0075] In the above formula (6), is the vertical inertia force of the supporting structure on the second accommodation part 20 under the seismic load, that is, the vertical inertia force of the first accommodation part 10 and / or the second accommodation part 20 on the second accommodation part 20 under the seismic load, is the vertical inertia force of the equipment in the reactor supported by the supporting structure on the second accommodation part 20 under seismic load, m s is the mass of the support structure and the mass of the coolant, m e is the mass of the equipment and coolant in the reactor supported by the support structure, a sv is the vertical acceleration at the center of mass of the support structure, a ev It is the vertical acceleration at the center of mass of the equipment in the reactor supported by the support structure. Those skilled in the art will understand that the center of mass is the center of mass of the material system, that is, an imaginary point on the material system where the mass is considered to be concentrated.

[0076] According to the embodiments provided by the present invention, when determining the center of mass position of the support structure and the equipment in the reactor supported by the support structure, it is also necessary to consider the influence of the mass of the material inside the support structure, for example, the influence of the mass of the coolant in the support structure. In some embodiments, when the equipment in the reactor supported by the support structure is a heat exchanger, then m e is the mass of the heat exchanger and the mass of the coolant in the support structure, m sis the mass of the support structure and the mass of the coolant. Similarly, the vertical acceleration at the center of mass of the support structure and the vertical acceleration at the center of mass of the equipment in the reactor supported by the support structure also need to consider the influence of the additional mass of the material in the support structure.

[0077]

[0078] In the above formula (7), is the horizontal inertia force of the supporting structure on the second accommodation part 20 under the seismic load, that is, the horizontal inertia force of the first accommodation part 10 and / or the second accommodation part 20 on the second accommodation part 20 under the seismic load, h is the horizontal inertial force of the equipment in the reactor supported by the supporting structure on the second accommodation part 20 under the earthquake load, s h is the distance between the center of mass of the support structure and the second receiving portion 20, e It is the distance from the center of mass of the equipment in the reactor supported by the support structure to the second accommodation part 20.

[0079] Those skilled in the art will appreciate that the distance between the center of mass of the support structure and the second accommodating portion 20 and the distance between the center of mass of equipment in the reactor supported by the support structure and the second accommodating portion 20 need to take into account the influence of the mass of the material in the support structure.

[0080] Specifically, the axial stress of the second accommodation portion 20 due to the gravity load is calculated by the following formula (8).

[0081]

[0082] Specifically, the axial stress of the first accommodation portion 10 and / or the transition portion 30 on the second accommodation portion 20 is calculated by the following formula (9).

[0083]

[0084] In the above formula (9), F vp M is the vertical force of the connecting portion and / or transition portion 30 on the second receiving portion 20, hp It is the bending moment generated by the connecting portion and / or the transition portion 30 on the second receiving portion 20 .

[0085] in,

[0086]

[0087] In the above formula (10), is the combined bending moment of the connecting portion and / or transition portion 30 to the second receiving portion 20, F hp h is the combined force in the horizontal direction of the connecting portion and / or the transition portion 30 on the second receiving portion 20,p is the distance from the connecting portion and / or transition portion 30 to the second accommodating portion 20. Optionally, the resultant bending moment of the connecting portion on the second accommodating portion 20 here may be the resultant bending moment of the connecting pipe load on the second accommodating portion 20, and the resultant force in the horizontal direction of the connecting portion on the second accommodating portion 20 may be the resultant force in the horizontal direction at the connecting pipe load position.

[0088] In an embodiment of the present invention, the shear stress on the second accommodation portion 20 is determined by the following steps:

[0089] Determine the seismic load and the shear stress of the connecting portion on the second accommodation portion 20 respectively;

[0090] The shear stress on the second accommodation portion 20 is determined according to the earthquake load and the shear stress of the connection portion on the second accommodation portion 20 .

[0091] Optionally, determining the shear stress on the second accommodation portion 20 further includes:

[0092] The shear stress of the transition portion 30 on the second receiving portion 20 is determined.

[0093] τ=τ i +τ p (11)

[0094] Among them, τ i is the shear stress of the seismic load on the second accommodation part 20, τ p is the shear stress of the connecting portion and / or transition portion 30 on the second receiving portion 20. Optionally, τ p It may be a shear stress caused by the pipe load on the bottom of the second accommodation portion 20 .

[0095] Specifically, the shear stress of the second accommodation portion 20 caused by the earthquake load is calculated by the following formula (12).

[0096]

[0097] In the above formula (12), F hi It is the resultant horizontal inertia force of the earthquake load on the second accommodation part 20.

[0098] in,

[0099]

[0100] In the above formula (13), a sh is the horizontal acceleration at the center of mass of the support structure, a ehIt is the horizontal acceleration at the center of mass of the equipment in the reactor supported by the support structure. Those skilled in the art will understand that the horizontal acceleration at the center of mass of the support structure and the horizontal acceleration at the center of mass of the equipment in the reactor supported by the support structure also need to consider the influence of the mass of the material in the support structure.

[0101] Specifically, the shear stress of the connecting portion and / or the transition portion 30 on the second receiving portion 20 is calculated by the following formula (14).

[0102]

[0103] Among them, T p is the torque at the connection and / or transition portion 30, I ρ is the polar moment of inertia of the cross section of the second receiving portion 20 .

[0104] In an embodiment of the present invention, the method further comprises:

[0105] The diameter of the first accommodation portion 10 is determined according to the diameter of the equipment to be arranged in the reactor.

[0106] An embodiment of the present invention provides a reactor, comprising:

[0107] A supporting structure for a reactor provided by an embodiment of the present invention;

[0108] a heat exchanger, the heat exchanger being fixed to a supporting structure; or

[0109] A power pump is fixed to the supporting structure.

[0110] The support structure for a reactor provided by an embodiment of the present invention increases the moment of inertia of the bearing interface of the support structure and improves the bending strength by making the diameter of the second accommodating part 20 larger than the diameter of the first accommodating part 10, so that the support structure can reliably support the equipment in the reactor under seismic loads.

[0111] Regarding the embodiments of the present invention, it should also be noted that, in the absence of conflict, the embodiments of the present invention and the features therein may be combined with each other to obtain new embodiments.

[0112] The above are only specific embodiments of the present invention, but the protection scope of the present invention is not limited thereto. The protection scope of the present invention shall be based on the protection scope of the claims.

Claims

1. A method for manufacturing a support structure for a reactor, characterized in that The method is used to manufacture a support structure for a reactor, wherein equipment in the reactor is arranged on the support structure via a connection portion. The support structure for a reactor comprises: A first receiving portion (10); a second accommodating portion (20), the second accommodating portion (20) being connected to the first accommodating portion (10), the first accommodating portion (10) and the second accommodating portion (20) being used to accommodate equipment in the reactor, and the coolant in the reactor being in contact with the equipment through the first accommodating portion (10) and / or the second accommodating portion (20); Wherein, the diameter of the second accommodating portion (20) is set to be larger than the diameter of the first accommodating portion (10), so as to improve the strength of the first accommodating portion (10) and / or the second accommodating portion (20); The method of manufacturing a support structure for a reactor comprises: Characterizing the relationship between the stress borne by the second accommodation portion (20) under earthquake conditions and the diameter of the second accommodation portion (20); Determining the maximum stress that the second receiving portion (20) can withstand according to the Tresca yield criterion; The diameter of the second accommodation portion (20) is determined according to the relationship between the stress borne by the second accommodation portion (20) under earthquake conditions and the diameter of the second accommodation portion (20), and the maximum stress that the second accommodation portion (20) can withstand. The diameter is such that the stress borne by the second accommodation portion (20) under earthquake conditions is less than or equal to the maximum stress that the second accommodation portion (20) can withstand; The support structure is manufactured according to the diameter of the second accommodating portion (20); the stress borne by the second accommodating portion (20) under earthquake conditions is the stress borne by the bottom of the second accommodating portion (20) under earthquake conditions.

2. The method according to claim 1, characterized in that: The support structure further comprises: A transition portion (30), the transition portion (30) being connected to a bottom end of the first accommodating portion (10) and a top end of the second accommodating portion (20), wherein the bottom end of the first accommodating portion (10) is arranged at a predetermined position above the top end of the second accommodating portion (20).

3. The method according to claim 1, characterized in that The support structure further comprises: A sealing portion (40), the sealing portion (40) being arranged at a connection between the first accommodating portion (10) and the second accommodating portion (20), and being used to prevent the coolant in the first accommodating portion (10) and / or the second accommodating portion (20) from flowing out from the connection.

4. The method according to claim 1, characterized in that: The first accommodating portion (10) is provided with a connecting portion (11), and the connecting portion (11) is used to allow the coolant in the reactor to flow into and / or out of the first accommodating portion (10).

5. The method according to claim 4, characterized in that The communication portion (11) comprises a plurality of through holes, and the plurality of through holes are evenly arranged in the first accommodation portion (10).

6. The method according to claim 1, characterized in that The equipment in the reactor includes a power pump and a heat exchanger.

7. The method according to claim 2, characterized in that Characterizing the relationship between the stress borne by the second accommodation portion (20) under earthquake conditions and the diameter of the second accommodation portion (20), including: Determining the stress borne by the second accommodating portion (20) under earthquake conditions according to the first principal stress and the third principal stress borne by the second accommodating portion (20), wherein the first principal stress is greater than or equal to the third principal stress; According to the stress borne by the second accommodation portion (20) under earthquake conditions, the relationship between the stress borne by the second accommodation portion (20) under earthquake conditions and the diameter of the second accommodation portion (20) is determined.

8. The method according to claim 7, characterized in that Also includes: According to the axial stress and the shear stress to which the second accommodation portion (20) is subjected, the first principal stress and the third principal stress to which the second accommodation portion (20) is subjected are determined.

9. The method according to claim 8, characterized in that The axial stress to which the second accommodation portion (20) is subjected is determined by the following steps: respectively determining the earthquake load, the gravity load and the axial stress of the connecting portion on the second receiving portion (20); The axial stress to which the second accommodating portion (20) is subjected is determined based on the seismic load, the gravity load and the axial stress of the connecting portion on the second accommodating portion (20).

10. The method according to claim 9, characterized in that Also includes: The axial stress of the transition portion (30) on the second accommodation portion (20) is determined.

11. The method according to claim 8, characterized in that The shear stress applied to the second accommodation portion (20) is determined by the following steps: respectively determining the seismic load and the shear stress of the connecting portion on the second receiving portion (20); The shear stress to which the second accommodating portion (20) is subjected is determined based on the seismic load and the shear stress of the connecting portion on the second accommodating portion (20).

12. The method according to claim 11, characterized in that Also includes: The shear stress of the transition portion (30) on the second receiving portion (20) is determined.

13. The method according to claim 1, characterized in that Also includes: The diameter of the first accommodation portion (10) is determined according to the diameter of equipment that needs to be arranged in the reactor.

14. A reactor, characterized in that: include: A support structure for a reactor manufactured according to the method according to any one of claims 1 to 13; a heat exchanger fixed to the support structure; A power pump is fixed to the support structure.

Citation Information

Patent Citations

  • Heavy metal cooling furnace

    JP2001264476A