CN113871043A - Method for replacing outer sleeve of control rod assembly in reactor core - Google Patents
Method for replacing outer sleeve of control rod assembly in reactor core Download PDFInfo
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- CN113871043A CN113871043A CN202111130855.2A CN202111130855A CN113871043A CN 113871043 A CN113871043 A CN 113871043A CN 202111130855 A CN202111130855 A CN 202111130855A CN 113871043 A CN113871043 A CN 113871043A
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- outer sleeve
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- 238000000034 method Methods 0.000 title claims abstract description 68
- 239000000463 material Substances 0.000 claims abstract description 55
- 238000000429 assembly Methods 0.000 claims abstract description 12
- 230000000712 assembly Effects 0.000 claims abstract description 12
- 239000000446 fuel Substances 0.000 claims description 15
- 239000003758 nuclear fuel Substances 0.000 claims description 8
- 239000011800 void material Substances 0.000 claims description 6
- 238000003780 insertion Methods 0.000 claims description 4
- 230000037431 insertion Effects 0.000 claims description 4
- 238000012546 transfer Methods 0.000 claims description 4
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims description 3
- 229910052708 sodium Inorganic materials 0.000 claims description 3
- 239000011734 sodium Substances 0.000 claims description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 description 4
- 239000006096 absorbing agent Substances 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 238000004064 recycling Methods 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/19—Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Automatic Assembly (AREA)
- Load-Engaging Elements For Cranes (AREA)
Abstract
The embodiment of the invention discloses a method for replacing an outer sleeve of a control rod assembly in a reactor core, wherein each group of control rod assemblies comprises a spent outer sleeve positioned at a working position of the reactor core and a moving body arranged in the spent outer sleeve; a first reserved vacancy and a second reserved vacancy are formed in the reactor core, wherein a temporary storage sleeve is arranged in the first reserved vacancy; the replacement method comprises the following steps: a new temporary storage sleeve placing step: placing a new temporary storage sleeve in the second reserved vacant position in the reactor core by using a special gripping apparatus for material replacement, wherein the temporary storage sleeve is used for temporarily storing the moving body moved out of the outer depleted sleeve in the process of replacing the outer depleted sleeve; the new temporary storage sleeve is used for temporarily storing the special gripping apparatus for material changing. According to the technical scheme of the embodiment of the invention, the two temporary storage sleeves are arranged, so that the control rod assembly in the reactor core of the reactor can be replaced conveniently.
Description
Technical Field
The invention relates to the technical field of reactors, in particular to a method for replacing an outer sleeve of a control rod assembly in a reactor core.
Background
The Chinese experimental fast reactor is the first sodium-cooled fast reactor in China, the appearance of the control rod assembly is the same as that of the fuel assembly, the structure of the control rod assembly is an integrated structure, and the refueling process flow of the control rod assembly is the same as that of the fuel assembly.
The control rod assembly in the demonstration fast reactor is improved on the basis of a Chinese experiment fast reactor structure, and adopts a split structure: the control rod assembly consists of a moving body and an outer sleeve, the moving body and the outer sleeve are independent from each other and have no connection relation, a rod bundle for absorbing neutrons is arranged in the moving body, the main body of the outer sleeve is a hexagonal sleeve, and the lower part of the outer sleeve is a cylindrical pin. In the reactor core, the outer sleeve pin is fixedly inserted in the vacancy of the small core plate header of the reactor core (namely the reactor core vacancy), and the moving body is arranged in the outer sleeve. The control rod driving mechanism grabs the head of the moving body and drives the moving body to move up and down in the outer sleeve, and the depth of the absorber rod bundle inserted into the reactor core is changed through the up-and-down movement of the moving body, so that the power in the reactor core is adjusted.
The existing refueling process of the control rod assembly mainly aims at the integral fuel assembly and is not suitable for the refueling operation of the control rod assembly with a split structure. Therefore, a new refueling process needs to be designed for the split control rod assembly to realize the replacement of the outer sleeve in the control rod assembly in the reactor core.
Disclosure of Invention
The application provides a method for replacing an outer sleeve of a control rod assembly in a reactor core, wherein each control rod assembly comprises a spent outer sleeve positioned at a working position of the reactor core and a moving body arranged in the spent outer sleeve; a first reserved vacancy and a second reserved vacancy are formed in the reactor core, wherein a temporary storage sleeve is arranged in the first reserved vacancy;
the replacement method comprises the following steps:
a new temporary storage sleeve placing step: placing a new temporary storage sleeve into the second reserved void within the reactor core using a special gripper for refueling,
the temporary storage sleeve is used for temporarily storing the moving body removed from the outer sleeve in the process of replacing the outer sleeve; the new temporary storage sleeve is used for temporarily storing the special gripping apparatus for material changing.
Drawings
Other objects and advantages of the present invention will become apparent from the following description of the invention which refers to the accompanying drawings, and may assist in a comprehensive understanding of the invention.
Fig. 1 is a schematic structural view of a gripping apparatus dedicated for reloading used in the method of replacing of the invention;
FIG. 2 is a flow chart illustrating the steps of inserting a new escrow sleeve according to an embodiment of the present invention;
FIG. 3 is a flow chart of a method of replacing an outer sleeve of a reactor in-core control rod assembly according to one embodiment of the present invention;
FIG. 4 is a flow chart illustrating a step of removing the spent outer sleeve according to an embodiment of the invention;
FIG. 5 shows a flowchart of a new outer sleeve insertion step according to an embodiment of the present invention;
FIG. 6 shows a flow chart of the refueling specific gripper removal step according to an embodiment of the present invention;
FIG. 7 is a flow chart illustrating a temporary storage sleeve removal step according to an embodiment of the present invention;
fig. 8 and 9 illustrate the change in core vacancy during the outer barrel replacement of the control rod assembly.
It is noted that the drawings are not necessarily to scale and are merely illustrative in nature and not intended to obscure the reader.
Description of reference numerals:
10. a core operating position; 11. an outer sleeve; 12. a moving body;
20. a reactor core working position 21 and a spent outer sleeve; 22. a moving body;
30. a first reserved vacancy; 31. temporarily storing the sleeve;
40. a second reserved vacancy;
51. a new temporary storage sleeve; 52. a gripping apparatus special for material changing;
61. a new outer sleeve; 62. a gripping apparatus special for material changing;
71. a new outer sleeve; 72. a gripping apparatus special for material changing;
101. grabbing a glove; 103. an operating head; 105. sleeving a sleeve; 106. a connecting section; 107. setting a sleeve; 108. a connector; 109. a first pin; 110. a first vertical slot; 111. a first inner boss; 112. a locking sleeve; 113. a second pin; 114. a spring; 115. a small grid plate header; 116. an outer sleeve.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the technical solutions of the present invention will be described clearly and completely with reference to the accompanying drawings of the embodiments of the present invention. It should be apparent that the described embodiment is one embodiment of the invention, and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the invention without any inventive step, are within the scope of protection of the invention.
It is to be noted that technical terms or scientific terms used herein should have the ordinary meaning as understood by those having ordinary skill in the art to which the present invention belongs, unless otherwise defined. If the description "first", "second", etc. is referred to throughout, the description of "first", "second", etc. is used only for distinguishing similar objects, and is not to be construed as indicating or implying a relative importance, order or number of technical features indicated, it being understood that the data described in "first", "second", etc. may be interchanged where appropriate.
In the related art, with the split control rod assembly, generally, the moving body is replaced every 1 year, and the outer sleeve is replaced every 1.5 years. That is, the movable body and the outer sleeve have different periods of use, and the movable body or the outer sleeve needs to be replaced individually when the movable body and the outer sleeve are replaced.
In the related art, the moving body and the outer sleeve have respective refueling processes. Typically, a new outer sleeve is carried into the core of the reactor by a special refueling gripper, and the spent outer sleeve is carried out of the reactor by the special refueling gripper.
Specifically, the special gripping apparatus for reloading can be locked or unlocked with the outer sleeve in the outer sleeve; in the reactor core, the operating head of the gripping and refueling special gripping apparatus can be grabbed by the refueling machine of the reactor refueling system to drive the gripping and refueling special gripping apparatus to move, so that the outer sleeve is driven to move. In addition, in the reactor core, the special refueling gripper and the outer sleeve can be locked or unlocked through the operation of the refueling machine of the reactor refueling system, so that after the new outer sleeve is placed in the reactor core vacancy, the new outer sleeve and the special refueling gripper can be unlocked, then the special refueling gripper and the spent outer sleeve are locked, and then the special refueling gripper is used for carrying the spent outer sleeve to move out of the reactor core.
FIG. 1 illustrates a refueling special grab for replacing a control rod assembly outer sleeve. Referring to fig. 1, the special gripping apparatus for reloading comprises an operating head 103 and a sleeve assembly; the operating head 103 is fixedly connected with the sleeve assembly; the operating head 103 is connected with the gripping sleeve 1 through an anti-skidding structure so as to ensure that the operating head 103 and the gripping sleeve 101 do not rotate relatively; the thimble assemblies are coupled to the control rod assembly outer thimble 116 by a first locking structure to lock and unlock the thimble assemblies to the control rod assembly outer thimble 116.
The operating head 103 can be consistent with the external dimension of the fuel assembly operating head, and mechanical equipment for transferring assemblies in the whole refueling system, such as a new assembly loader, a transferring machine, a pool operating machine and the like, can grab the operating head 103 of the sleeve assembly. The ferrule assembly may include an upper ferrule 105, a connection section 106, a lower ferrule 107, and a connector 108 fixedly connected together.
The first locking structure includes a first pin 109 and a first vertical slot 110; the first pin 109 is disposed on the thimble assembly and the first vertical slot 110 is disposed in the control rod assembly outer sleeve 116. A first pin 109 is provided on the connector 108 for locking and unlocking in cooperation with a first vertical slot 110 in a control rod assembly outer sleeve 116. A first inner boss 111 is further arranged in the first vertical groove 110; the first pin 109 is slidable along a first vertical slot 110 to the bottom of the first vertical slot 110 and is rotatable to be captured by the first inner ledge 111 to lock the control rod assembly outer sleeve 116 to the thimble assembly. The first pin 109 is provided with a flat surface for facilitating engagement with the first inner boss 111.
Control rod assembly outer sleeve 116 may also be connected to small grid header 115 by a second locking structure to lock or unlock control rod assembly outer sleeve 116 to small grid header 115; the sleeve assembly is also in control connection with the second locking structure; when the thimble assembly is locked with control rod assembly outer sleeve 116, the control rod assembly outer sleeve 116 is unlocked with small grid header 115; when the thimble assembly is unlocked from the control rod assembly outer sleeve 116, the control rod assembly outer sleeve 116 is locked to the small grid header 115.
The second locking structure comprises a locking sleeve 112 and an elastic component; the locking sleeve 112 and resilient member are disposed in a prong of the control rod assembly outer sleeve 116; the locking sleeve 112 can move axially relative to the pin; the locking sleeve 112 can be pressed against the sleeve assembly by the elastic member to press the first pin 109 against the first inner boss 111; the thimble assemblies are capable of rotating the lock sleeve 112 to effect locking or unlocking of the control rod assembly outer sleeve 116 with the small grid header 115.
A second pin 113 is arranged on the locking sleeve 112, so that the locking and unlocking of the outer sleeve 116 and the small grid plate header 115 are realized; a locking through hole is formed in a pin of an outer sleeve 116 of the control rod assembly, and a second vertical groove with a second inner boss is formed in the small grid plate header 115; the second pin 113 passes through the locking through hole, is capable of sliding along a second vertical slot to the bottom of the second vertical slot, and is capable of being stopped by the second inner boss after rotation to lock the control rod assembly outer sleeve 116 with the small grid plate header 115.
The locking sleeve 112 is provided with a hole matching with the lower part of the connector 108 so that the lower part of the connector 108 can be inserted into the hole and the locking sleeve 112 can be rotated. The lower end of the connector 108 is hexagonal and can match with the hexagonal groove of the locking sleeve 112 in the pin of the outer sleeve 116.
Through the interlocking relation established between the sleeve assembly and the outer sleeve 116, and between the outer sleeve 116 and the small grid plate header 115, when the sleeve assembly and the outer sleeve 116 are locked, the outer sleeve 116 and the small grid plate header 115 are unlocked, when the sleeve assembly and the outer sleeve 116 are unlocked, the outer sleeve 116 and the small grid plate header 115 are locked, and through the interlocking relation, the outer sleeve 116 can be ensured to be drawn out from the small grid plate header 115 only when the sleeve assembly and the outer sleeve 116 are locked, so that the falling accident is avoided when the outer sleeve 116 is moved in the reactor core.
In the reactor core, the moving body can be driven to move by an operating head of the moving body grabbed by a refueling machine of the refueling system in the reactor. And in the reactor core, the transfer of the special refueling gripper, the transfer of the moving body and the locking and unlocking of the special refueling gripper and the outer sleeve are realized through the cooperation of a refueling machine and a cock of the refueling system in the reactor core.
Due to the fact that equipment in the in-pile and out-pile refueling systems is as follows: the handling lifting machine, the spent component conversion barrel and other equipment are used for receiving a spent fuel component or a spent outer sleeve, and the single special gripping apparatus for changing materials lacks the interface size with the equipment, so the single special gripping apparatus for changing materials cannot transport out the reactor core, the gripping apparatus must be locked with the outer sleeve or the temporary storage sleeve, and the reactor core can be transported out only after the appearance size is complete. Therefore, the problem of removing the refueling gripper from the reactor must be considered when designing the outer sleeve for replacement.
In the related art, in order to facilitate replacement of the outer sleeve, a reserved empty space is provided in the storage well of the reactor core; however, the lower limit of the loading and unloading elevator can be occupied for a long time in the process of replacing the outer sleeve, and the locking and unlocking operation of the gripping apparatus special for material replacement and the outer sleeve is positioned at the loading and unloading elevator. If the clamping stagnation phenomenon occurs after the gripping device special for material changing is unlocked from the outer sleeve, the outer sleeve cannot be limited to move in the vertical direction in the lifting barrel of the charging hoister, the outer sleeve is brought out from the lifting barrel of the charging hoister in the process of drawing out the gripping device special for material changing, and the safety is to be improved.
The invention provides a novel method for replacing an outer sleeve of a split control rod assembly. In the process of the invention, two reserved empty spaces are provided at the reactor core storage well (i.e. the small grid header): a first reserved vacancy and a second reserved vacancy. Wherein a temporary storage sleeve is arranged in the first reserved vacant site; the second reserved vacant site is empty.
The method for replacing the outer sleeve of the control rod assembly in the reactor core provided by the embodiment of the invention comprises the following steps:
a new temporary storage sleeve placing step: placing a new temporary storage sleeve in the second reserved void in the reactor core with a special refueling gripper that can lock or unlock with an outer sleeve,
the temporary storage sleeve is used for temporarily storing the moving body removed from the outer sleeve in the process of replacing the outer sleeve; the new temporary storage sleeve is used for temporarily storing the special gripping apparatus for material changing.
According to the technical scheme of the embodiment of the invention, the two reserved vacant positions are arranged, and the temporary storage sleeve specially used for temporarily storing the moving body moved out of the outer sleeve and the new temporary storage sleeve used for temporarily storing the special gripping apparatus for material replacement are respectively arranged at the reserved vacant positions, so that the outer sleeve of the control rod assembly in the reactor core of the reactor can be conveniently replaced.
Fig. 2 shows a flow chart of a new insertion step of the escrow sleeve according to an exemplary embodiment of the invention.
Referring to fig. 2, the new escrow sleeve inserting step may include:
step 202, providing a special gripping apparatus for material changing, wherein the special gripping apparatus for material changing can be locked or unlocked with an outer sleeve in the outer sleeve;
step 204, locking the special refueling gripping apparatus with a new temporary storage sleeve in a new fuel storehouse of the reactor;
and 206, transferring the special refueling gripper and the new temporary storage sleeve which are locked together to the reactor core through a refueling system and placing the special refueling gripper and the new temporary storage sleeve in a second reserved vacant position in the reactor core.
In step S202, a refueling special gripper may be provided having a structure as shown in fig. 1, and the refueling special gripper may be locked or unlocked with the outer sleeve by the engagement of the pin and the groove. Of course, those skilled in the art may also adopt another gripper for material change according to the function of the gripper for material change.
It is easy to understand that the temporary storage sleeve and the new temporary storage sleeve have the same or similar structures with the outer sleeve of the control rod assembly, so that the locking or unlocking of the temporary storage sleeve and the temporary storage sleeve (including the new temporary storage sleeve and the temporary storage sleeve in the first reserved vacant position) and the locking or unlocking of the temporary storage sleeve and the outer sleeve (including the new outer sleeve and the spent outer sleeve) can be realized by using the special material changing gripping device with the same structure.
In step S204, the refueling gripper may be locked with the new staging sleeve in a new fuel depot. The new temporary storage sleeve placing step further comprises: the locked special gripping apparatus for reloading and the new temporary storage sleeve are transported to a reactor hall through a new assembly process transportation system; and then the locked special refueling gripping device and the new temporary storage sleeve are transported to the reactor core by utilizing the in-core and out-core refueling system.
In step S206, an operation head of a special refueling gripper is gripped by a refueling machine of the in-reactor refueling system in the reactor core, and the locked special refueling gripper and the new temporary storage sleeve are placed in a second reserved vacant position in the reactor core.
FIG. 3 is a flow chart of a method of replacing an outer sleeve of a reactor in-core control rod assembly according to one embodiment of the invention. As shown in fig. 3, the replacement method according to the embodiment of the present application includes:
step S302 of inserting a new temporary storage sleeve: placing a new temporary storage sleeve into the second reserved void within the reactor core using a special refueling gripper.
Moving body moving-out step S304: moving a moving body in a spent outer sleeve to be replaced to the temporary storage sleeve;
taking out the spent outer sleeve S306: moving the spent sleeve out of the reactor by using a special gripping apparatus for refueling;
the new outer sleeve is inserted into step S308: placing a new outer sleeve in a vacant working position after the spent outer sleeve is moved out by using another special gripping apparatus for reloading;
a material changing special gripping apparatus moving-out step S310: moving the other special material changing gripping apparatus to the new temporary storage sleeve; and
moving body moving back to step S312: moving the mobile body back into the new outer sleeve.
In the above replacement method, the sequence between the moving body moving-out step S304 and the new temporary storage sleeve inserting step S302 may be changed. That is, the moving body removing step S304 may be performed first, and then the new temporary storage sleeve inserting step S302 may be performed, or the new temporary storage sleeve inserting step S302 may be performed first, and then the moving body removing step S304 may be performed.
The moving body moving-out step S304 includes: and in the reactor, the moving body is moved from the outer depleted sleeve to the temporary storage sleeve for temporary storage through the cooperation of a refueling machine and a cock of the refueling system in the reactor.
Fig. 4 shows a flowchart of the outer sleeve extracting step S306 according to an embodiment of the present invention. Referring to fig. 4, the outer sleeve extracting step S306 may include:
step 402, unlocking the special material changing gripping apparatus and the new temporary storage sleeve;
step 404, transferring the special gripping apparatus for changing materials into a spent outer sleeve to be changed, and locking the gripping apparatus with the spent outer sleeve;
and 406, removing the locked refueling special gripping device and the outer sleeve out of the reactor from the vacancy of the reactor core.
In step 402, the gripper dedicated to material change can be unlocked from the new temporary storage sleeve by using the cooperation of the refueling machine and the cock of the in-pile refueling system, and the new temporary storage sleeve is locked with the small grid plate header while the gripper dedicated to material change is unlocked from the new temporary storage sleeve.
In step 404, the unlocked special refueling gripper can be transferred from the new temporary storage sleeve to the to-be-replaced outer sleeve by using the refueling machine of the in-pile refueling system (the moving body in the outer sleeve is moved out to the temporary storage sleeve); and then, the special gripping apparatus for changing the materials can be locked with the outer sleeve without charge by utilizing the matching of the material changing machine and the cock of the in-pile material changing system, and the outer sleeve without charge is unlocked with the small grid plate header while the special gripping apparatus for changing the materials is locked with the outer sleeve without charge.
In step 406, the locked special refueling gripping apparatus and the outer casing can be transported to the outside of the reactor by using a loading and unloading elevator.
The special gripping apparatus for refueling and the spent outer sleeve which are moved out of the reactor can be further transported into a spent fuel pool through a refueling system. After the outer spent sleeve is placed in the storage grillwork, the special gripping apparatus for refueling and the outer spent sleeve are unlocked, then the special gripping apparatus for refueling is cleaned and dried, and then the material is transported to a new fuel warehouse for recycling.
In step S406, the reactor core operating position where the outer casing sleeve is located is vacated while the refueling special gripper and the outer casing sleeve are transported to the outside of the reactor.
Fig. 5 shows a flowchart of the new outer sleeve inserting step S308 according to an embodiment of the present invention. Referring to fig. 5, the new outer sleeve setting step S308 may include:
step 502, locking another refueling special gripping apparatus with a new outer sleeve in a new fuel storehouse outside the reactor;
and step 504, placing the other refueling special gripping device and the new outer sleeve locked together in a working position vacated after the outer sleeve depleted core is replaced.
In step 502, another material change special gripper may be a new material change special gripper, or a material change special gripper that has been cleaned and dried before being used.
Fig. 6 shows a flowchart of the refueling specific gripper removing step S310 according to an embodiment of the present invention. Referring to fig. 6, the material change-dedicated gripper removing step S310 may include:
step 602, unlocking the other special refueling gripping apparatus with the new outer sleeve;
step 604, transferring the another gripper dedicated for reloading into the new temporary storage sleeve.
The moving body moving back step S312 includes: and transferring the moving body in the temporary storage sleeve into the new outer sleeve to complete the replacement of the spent outer sleeve.
It will be appreciated that the present application, through steps 304 through 312, ultimately completes the replacement of the outer sleeves of a set of control rod assemblies.
The above process is repeated, i.e. step 304 to step 312 are repeated, and all the outer sleeves can be replaced in sequence.
Therefore, after the moving body moves back to step S312, the replacement method further includes: and repeating the moving body moving-out step S304, the outer sleeve taking-out step S306, the new outer sleeve placing step S308, the special material changing gripper moving-out step S310 and the moving body moving-back step S312 in sequence until the replacement of all the outer sleeves is completed.
In some embodiments, the staging sleeve is pre-positioned at the reactor core preparation void by manual operation prior to the reactor core being sealed and sodium filled. That is, the sleeve of keeping in sleeve and control rod subassembly is placed in the reactor core vacancy simultaneously before the sealed sodium that fills of reactor core, like this, when outer sleeve service life expires and needs to be changed, also need change the sleeve of keeping in.
In other embodiments, the staging sleeve is a new staging sleeve placed in the reserved void of the reactor core during the new staging sleeve insertion step when the outer sleeve of the control rod assembly was last replaced using the replacement method of the present application. That is, in other embodiments, both the escrow sleeve and the outer sleeve of the control rod assembly have been replaced. In such an embodiment, when the service life of the replaced outer sleeve has expired and a replacement is required, the replacement of the temporary sleeve is also required.
Therefore, after the replacement of all the outer sleeves is completed, the replacement method further comprises the following steps:
taking out the temporary storage sleeve: and moving the temporary storage sleeve out of the reactor by using a special gripping apparatus for material changing.
Fig. 7 shows a flow chart of the removal step of the escrow sleeve according to an embodiment of the invention. Referring to fig. 7, the escrow sleeve withdrawing step includes:
step 702, transferring the special gripping apparatus for material changing in the new temporary storage sleeve into the temporary storage sleeve to be locked with the temporary storage sleeve;
and 704, moving the locked special material changing gripping apparatus and the temporary storage sleeve out of the reactor to complete the replacement of the temporary storage sleeve.
A method for replacing an outer sleeve of a reactor in-core control rod assembly according to embodiments of the present invention is described in detail below with reference to fig. 8 and 9.
1. In the new fuel warehouse, the special gripping apparatus for refueling and the new temporary storage sleeve are locked firstly, and then the locked special gripping apparatus for refueling and the new temporary storage sleeve are transported to a reactor hall through a new assembly process transportation route in the existing assembly refueling process route.
2. And after the two are transported to a reactor hall, the locked special material changing gripping apparatus and the new temporary storage sleeve are transported to the reactor core of the reactor through the outside-reactor and inside-reactor material changing process routes in the existing component material changing process routes.
3. Within the reactor core:
the initial state of the reactor core is shown in fig. a. The outer sleeve 11 and the moving body 12 are provided in the core station 10, and the outer sleeve 21 and the moving body 22 are provided in the core station 20. The reactor is provided with a first reserved vacancy 30 and a second reserved vacancy 40, and a temporary storage sleeve 31 is arranged in the first reserved vacancy 30.
(1) Transferring the locked special refueling gripper 52 and the new temporary storage sleeve 51 to the second reserved vacant site 40 in the core by the cooperation of the refueling machine and the cock of the in-core refueling system (see fig. b);
(2) transferring the moving body 12 of the control rod assembly in the reactor core, which needs to replace the outer sleeve 11, into the temporary storage sleeve 31 at the first reserved vacant position 30 by the cooperation of the refueling machine and the cock, and at the moment, vacating the outer sleeve 11 which needs to be replaced (see figure c);
(3) unlocking the special refueling gripper 52 locked at the second reserved vacant position 40 from the new temporary storage sleeve 51 by the operation of the refueling machine, then transferring the special refueling gripper 52 into the outer spent sleeve 11 vacant in the core, and locking the special refueling gripper 52 with the outer spent sleeve 11 (see fig. d);
(4) the locked refueling special gripper 52 and the outer sleeve 11 are transported out of the reactor, and the core operating position 10 is vacated (see figure e).
4. The special refueling gripping apparatus 52 and the spent outer sleeve 11 which are transported out of the reactor are transported to a spent fuel pool for storage through a spent component process transportation route in the existing component refueling process route.
5. In the new fuel reservoir, the refueling gripper 62 is locked with the new outer sleeve 61 and then transported to the reactor lobby through a new component handling transport route of the existing component refueling handling routes.
6. After the two are transported to a reactor hall, the locked special refueling gripper 62 and the new outer sleeve 61 are transported to the reactor core through the outside-reactor and inside-reactor refueling process routes in the existing component refueling process routes.
7. Within the reactor:
(1) placing the locked refueling special gripper 62 and the new outer sleeve 61 at the core operating position 10 (see fig. f) by the cooperation of the cock and the refueling machine;
(2) by means of the operation of the cock and the refueling machine, the special refueling gripper 62 is unlocked from the new outer sleeve 61 and the special refueling gripper 62 is transferred into the new temporary storage sleeve 51 located in the second reserved empty space 40, the new outer sleeve 61 being empty (see fig. g);
(3) by the operation of the stocker, the moving body 12 is put into the new outer sleeve 61, and the outer sleeve replacement of the set of control rod assemblies is completed (see fig. h).
Then, the replacement of the outer sleeve of the next set of control rod assemblies is initiated.
8. Within the reactor:
(1) transferring the moving body 22 of the control rod assembly, which needs to replace the outer sleeve 21, in the core into the temporary storage sleeve 31 at the first reserved vacant position 30 by matching the refueling machine with the cock, and at the moment, emptying the outer sleeve 21 which needs to be replaced (see fig. i);
(3) transferring the special refueling gripper 62 at the second reserved vacant position 40 from the new temporary storage sleeve 51 into the outer depleted sleeve 21 by the operation of the refueling machine, and locking the special refueling gripper 52 with the outer depleted sleeve 21 (see fig. j);
(4) the locked refueling special gripper 62 and the outer sleeve 21 are transported out of the reactor, and the core operating position 20 is vacated (see fig. k).
9. The special refueling gripper 62 and the spent outer sleeve 21 which are transported out of the reactor are transported to a spent fuel pool for storage through a spent component process transportation route in the existing component refueling process route.
10. In the new fuel reservoir, the refueling gripper 72 is locked with the new outer sleeve 71 and then transported to the reactor lobby through a new component handling transport route of the existing component refueling handling routes.
11. After the two are transported to a reactor hall, the locked special refueling gripper 72 and the new outer sleeve 71 are transported to the reactor core through the outside-reactor and inside-reactor refueling process routes in the existing component refueling process routes.
12. Within the reactor:
(1) placing the locked refueling special gripper 72 and the new outer sleeve 71 to the core operating position 20 (see fig. l) through the cooperation of the cock and the refueling machine;
(2) by means of the operation of the cock and the refueling machine, the gripping means 72 specific to refueling is unlocked from the new outer sleeve 71 and the gripping means 72 specific to refueling is transferred into the new temporary storage sleeve 51 located in the second reserved empty space 40, the new outer sleeve 71 being empty (see fig. m);
(3) by the operation of the stocker, the moving body 22 is put into the new outer sleeve 71, and the outer sleeve replacement of the set of control rod assemblies is completed (see fig. n).
And completely replacing the outer sleeves of all the control rod assemblies according to the replacement method. Thereafter, the refueling gripper 72 and the staging sleeve 31 are removed from the reactor. Specifically, the method comprises the following steps:
13. within the reactor:
(1) by means of a change-out operation, the special change gripper 72 located in the new staging sleeve 51 is transferred into the staging sleeve 31, the special change gripper 72 being locked with the staging sleeve 31 by means of a cock and change-out operation (see fig. o);
(2) the locked special gripping apparatus 72 for refueling and the temporary storage sleeve 31 are moved out of the reactor by the operation of the cock and the refueling machine, the temporary storage sleeve is replaced (see fig. p), and the new temporary storage sleeve 51 left at the second reserved vacant core position 40 is used as the temporary storage sleeve.
Therefore, the replacement method provided by the embodiment of the invention has at least the following beneficial effects:
(1) the replacement operation of the outer sleeve of the control rod assembly can be realized under the operation of the existing equipment of the refueling system; the refueling process flow does not influence the refueling operation of the fuel assembly;
(2) in the preferred embodiment of the present application, the temporary storage sleeve 31 occupying a long time is arranged at one of the vacant positions, and before the outer sleeve of the control rod assembly is replaced, a new temporary storage sleeve 51 is arranged at the other vacant position, so that after all the control rod assemblies are replaced, the temporary storage sleeve 31 can be carried and moved out of the reactor by using the special gripping apparatus 72 for refueling which is left in the reactor, and therefore only the new temporary storage sleeve 51 is left at the two vacant positions in the reactor, and the replacement of the temporary storage sleeve 31 is realized.
(3) Compared with the replacement method in the related art, the temporary storage sleeve specially used for temporarily storing the moving body moved out of the outer sleeve and the new temporary storage sleeve used for temporarily storing the special material replacement gripping apparatus are arranged, so that the operation of moving the moving body out of the outer sleeve and moving the moving body back into the new outer sleeve is not interfered by the special material replacement gripping apparatus. The whole replacement process is simplified in design, operation steps are reduced, and the replacement efficiency of the control rod assembly is improved.
It should also be noted that, in the case of the embodiments of the present invention, features of the embodiments and examples may be combined with each other to obtain a new embodiment without conflict.
The above description is only an embodiment of the present invention, but the scope of the present invention is not limited thereto, and the scope of the present invention is subject to the scope of the claims.
Claims (15)
1. A method of replacing an outer sleeve of a control rod assembly within a reactor core, wherein each set of control rod assemblies includes a spent outer sleeve at a core operating position and a mobile body disposed within the spent outer sleeve; a first reserved vacancy and a second reserved vacancy are formed in the reactor core, wherein a temporary storage sleeve is arranged in the first reserved vacancy;
the replacement method comprises the following steps:
a new temporary storage sleeve placing step: placing a new temporary storage sleeve into the second reserved void within the reactor core using a special gripper for refueling,
the temporary storage sleeve is used for temporarily storing the moving body removed from the outer sleeve in the process of replacing the outer sleeve; the new temporary storage sleeve is used for temporarily storing the special gripping apparatus for material changing.
2. The replacement method according to claim 1, further comprising:
moving-out step: moving a moving body in a spent outer sleeve to be replaced to the temporary storage sleeve;
taking out the spent outer sleeve: moving the outer spent sleeve out of the reactor by using a special gripping apparatus for refueling;
a new outer sleeve inserting step: placing the new outer sleeve into a vacant position left after the outer sleeve is moved out by using another special gripping apparatus for reloading;
moving out the special gripping apparatus for changing materials: moving the other special material changing gripping apparatus to the new temporary storage sleeve; and
moving back the moving body: moving the mobile body back into the new outer sleeve.
3. The replacing method according to claim 2, wherein the moving body removing step includes: and in the reactor, the moving body is moved from the outer depleted sleeve to the temporary storage sleeve for temporary storage through the cooperation of a refueling machine and a cock of the refueling system in the reactor.
4. The changing method according to claim 2, wherein the gripper dedicated for changing material can be locked or unlocked with a new temporary storage sleeve, a spent outer sleeve, and the spent outer sleeve removing step comprises:
unlocking the gripping apparatus special for reloading and the new temporary storage sleeve;
transferring the special gripping apparatus for replacing materials into the outer sleeve to be replaced, and locking the gripping apparatus with the outer sleeve; and
and removing the locked refueling special gripping tool and the outer sleeve out of the reactor from the working position of the reactor core.
5. The changing method according to claim 4, wherein the grip dedicated for changing is also lockable or unlockable with a new outer sleeve, the new outer sleeve insertion step comprising:
locking the another refueling specific gripper with the new outer sleeve within a new fuel depot outside the reactor;
and placing the other refueling special gripping tool and the new outer sleeve which are locked together in a working position vacated after the spent outer sleeve is removed.
6. The method of changing as defined in claim 5, wherein the step of removing the refueling special gripper comprises:
unlocking the another refueling special gripper with the new outer sleeve;
and transferring the other special material changing gripping device into the new temporary storage sleeve.
7. The replacing method according to claim 6, wherein the moving body moving back step includes:
and transferring the moving body in the temporary storage sleeve into the new outer sleeve to complete the replacement of the spent outer sleeve.
8. The replacing method according to claim 2, wherein after the moving body moving back step, the replacing method further comprises: and sequentially repeating the moving body moving-out step, the outer sleeve replacing step, the new outer sleeve placing step, the material changing special gripping apparatus moving-out step and the moving body moving-back step until the replacement of all the outer sleeves is completed.
9. The replacement method according to claim 1, wherein the escrow sleeve is manually placed in a reserved space of the reactor core before the reactor core is sealed and filled with sodium; or when the temporary storage sleeve is the outer sleeve of the control rod assembly replaced last time, the temporary storage sleeve is placed in a new temporary storage sleeve of the reactor core in the new temporary storage outer sleeve placing step.
10. The replacement method according to claim 1, wherein after completing replacement of all of the spent outer sleeve, the replacement method further comprises:
taking out the temporary storage sleeve: and moving the temporary storage sleeve out of the reactor by using a special gripping apparatus for material changing.
11. The method of changing according to claim 10, wherein the grip dedicated for changing is also lockable or unlockable with a temporary storage sleeve, the temporary storage sleeve removal step comprising:
transferring the special material changing gripping apparatus positioned in the new temporary storage sleeve into the temporary storage sleeve, and locking the temporary storage sleeve with the temporary storage sleeve; and
and moving the locked special material changing gripping apparatus and the temporary storage sleeve out of the reactor to complete the replacement of the temporary storage sleeve.
12. The method of changing as claimed in claim 1, wherein the step of inserting a new escrow sleeve comprises:
locking the special material changing gripping apparatus with a new temporary storage sleeve in a new fuel storehouse outside the reactor;
and transferring the special refueling gripping device and the new temporary storage sleeve which are locked together to a reactor core through a refueling system and placing the reactor core in the second reserved vacant position.
13. The method of changing as claimed in claim 12, wherein said locking the refueling gripper with the new staging sleeve outside the reactor comprises:
locking the special material changing gripping apparatus with the new temporary storage sleeve in a new fuel storehouse;
the new temporary storage sleeve placing step further comprises:
the locked special gripping apparatus for reloading and the new temporary storage sleeve are transported to a reactor hall through a new assembly process transportation system; and
and (4) transporting the locked special gripping apparatus for refueling and the new temporary storage sleeve to a second reserved vacant site of the reactor core through an in-reactor refueling system and an out-reactor refueling system.
14. The replacement method according to claim 2,
the new temporary storage sleeve, the new outer sleeve and the spent outer sleeve have the same structure and can be locked and unlocked with the special gripping apparatus for material changing.
15. The replacement method according to claim 14, wherein the transfer of the refueling gripper, the transfer of the moving body, and the locking and unlocking of the refueling gripper with the outer sleeve are carried out within the reactor core by cooperation of a refueling machine and a cock of the reactor refueling system.
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| CN202111130855.2A CN113871043B (en) | 2021-09-26 | 2021-09-26 | Method for replacing outer sleeve of control rod assembly in reactor core |
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| CN202111130855.2A CN113871043B (en) | 2021-09-26 | 2021-09-26 | Method for replacing outer sleeve of control rod assembly in reactor core |
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