CN113871041B - Method for installing, removing and replacing control rod assembly - Google Patents
Method for installing, removing and replacing control rod assembly Download PDFInfo
- Publication number
- CN113871041B CN113871041B CN202111129136.9A CN202111129136A CN113871041B CN 113871041 B CN113871041 B CN 113871041B CN 202111129136 A CN202111129136 A CN 202111129136A CN 113871041 B CN113871041 B CN 113871041B
- Authority
- CN
- China
- Prior art keywords
- sleeve
- special
- changing
- materials
- refueling
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 238000000034 method Methods 0.000 title claims abstract description 98
- 239000000463 material Substances 0.000 claims abstract description 165
- 239000011800 void material Substances 0.000 claims abstract description 16
- 239000000446 fuel Substances 0.000 claims description 25
- 230000000712 assembly Effects 0.000 claims description 12
- 238000000429 assembly Methods 0.000 claims description 12
- 239000000523 sample Substances 0.000 claims 2
- 239000000758 substrate Substances 0.000 claims 2
- 238000009434 installation Methods 0.000 abstract description 21
- 230000008569 process Effects 0.000 description 29
- 239000003758 nuclear fuel Substances 0.000 description 7
- 230000009471 action Effects 0.000 description 6
- 230000008859 change Effects 0.000 description 4
- 238000000605 extraction Methods 0.000 description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 description 3
- 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 description 2
- 230000013011 mating Effects 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 1
- 239000011358 absorbing material Substances 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 238000011900 installation process Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
Classifications
-
- 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
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Load-Engaging Elements For Cranes (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
A control rod assembly installation method, a control rod assembly removal method and a control rod assembly replacement method. The control rod assembly includes a moving body and an outer sleeve. Wherein a method of installing a control rod assembly within a reactor core includes: the outside of the reactor locks the special tool for changing the materials with the outer sleeve; placing the locked refueling special tool and the outer sleeve at a core void within the reactor; unlocking the special tool for changing the materials and the outer sleeve; and removing the refueling special tool from within the outer sleeve. The invention provides an installation method suitable for a split control rod assembly.
Description
Technical Field
The invention relates to the technical field of reactors, in particular to a method for installing a control rod assembly in a reactor core, a method for taking the control rod assembly out of the reactor core and a method for replacing the control rod assembly.
Background
The Chinese experimental fast reactor is a first domestic sodium-cooled fast reactor, 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 process flow of the material changing 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 the structure of the Chinese experimental fast reactor, and adopts a split type structure: the control rod assembly consists of a moving body and an outer sleeve, wherein the moving body and the outer sleeve are mutually independent, a rod bundle for absorbing neutrons is arranged in the moving body, the outer sleeve body is a hexagonal sleeve, and the lower part of the hexagonal sleeve is a cylindrical pin. In the reactor core, the pin of the outer sleeve is fixedly inserted in the empty space (i.e. core empty space) of the small grid plate header of the reactor core, and the movable 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 bundles 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 control rod assembly refueling process is mainly aimed at an integral fuel assembly and is not suitable for the refueling operation of a control rod assembly with a split structure. Therefore, a new refueling process is designed for the split control rod assembly, and replacement, installation or removal of the control rod assembly in the reactor core is realized.
Disclosure of Invention
A first aspect of the present invention provides a method of installing a control rod assembly within a reactor core, the control rod assembly including a moving body and an outer sleeve, the method comprising:
Providing a reloading special tool which can be locked or unlocked with the outer sleeve in the outer sleeve;
Locking the refueling special tool with the outer sleeve outside the reactor;
Placing the locked refueling special tool and the outer sleeve at a core working position within the reactor core;
unlocking the special tool for changing the materials and the outer sleeve; and
The special tool for changing the materials is removed from the outer sleeve.
The second aspect of the invention provides a method for taking a control rod assembly out of a reactor core, wherein the control rod assembly comprises a moving body and an outer sleeve, a first reserved vacancy and a second reserved vacancy are reserved in the reactor core, and a temporary storage sleeve for temporarily storing a special tool for material replacement is arranged in the first reserved vacancy; the method comprises the following steps:
Providing a sleeve special for material changing, wherein the movable body can be locked or unlocked with the sleeve special for material changing in the sleeve special for material changing;
providing a reloading special tool which can be locked or unlocked with the outer sleeve and the reloading special sleeve respectively in the outer sleeve and the reloading special sleeve;
locking the special tool for changing the materials with the sleeve for changing the materials outside the reactor;
Placing the locked refueling special tool and the refueling special sleeve at the second reserved void within the reactor core;
transferring the moving body into the temporary storage sleeve;
unlocking the special tool for changing the materials and the special sleeve for changing the materials;
transferring the special tool for material changing into the outer sleeve and locking the special tool with the outer sleeve; and
And removing the locked refueling special tool and the outer sleeve from the reactor core.
A third aspect of the present invention provides a method of replacing a control rod assembly, the control rod assembly including a moving body and an outer sleeve, the method comprising:
According to the extraction method, removing the special tool for changing the materials and the spent outer sleeve from the reactor, and removing the spent mobile body and the special sleeve for changing the materials from the reactor;
according to the installation method described above, a new outer sleeve is moved into the core working position of the reactor core, and a new mobile is moved into the new outer sleeve.
Drawings
Other objects and advantages of the present invention will become apparent from the following description of the invention with reference to the accompanying drawings, which provide a thorough understanding of the present invention.
FIG. 1 is a schematic diagram of a specific tool for changing materials according to an embodiment of the present application;
FIG. 2 is a cross-sectional view of the engagement between the glove, small grid header, locked reload tool and outer sleeve;
FIG. 3 is a cross-sectional view taken along the direction A-A in FIG. 2;
FIG. 4 is a schematic view of a cartridge for use in a reload according to an embodiment of the application;
FIG. 5 is a cross-sectional view taken along the direction B-B in FIG. 4;
FIG. 6 is a mating view of the glove, small grid header, locked reload sleeve and mobile body;
FIG. 7 is a cross-sectional view taken along the direction C-C in FIG. 6;
FIG. 8 is an enlarged partial view of region D of FIG. 6;
FIG. 9 is a flow chart of a method of installing a control rod assembly within a reactor core in accordance with one embodiment of the invention;
FIG. 10 is a flow chart of a method of installing a control rod assembly within a reactor core in accordance with another embodiment of the invention;
FIG. 11 illustrates changes in the core during installation of control rod assemblies within the reactor core;
FIG. 12 is a flow chart of a method of removing a control rod assembly from a reactor core in accordance with one embodiment of the present invention;
FIG. 13 illustrates changes in the core during the removal of control rod assemblies from the reactor core; and
FIG. 14 is a flow chart of a method of replacing a control rod assembly according to one embodiment of the present invention.
It should be noted that the drawings are not necessarily to scale, but are merely shown in a schematic manner that does not affect the reader's understanding.
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 clearly and completely described below with reference to the accompanying drawings of the embodiments of the present invention. It will be apparent that the described embodiments are one embodiment, but not all embodiments, of the present invention. All other embodiments, which can be made by a person skilled in the art without creative efforts, based on the described embodiments of the present invention fall within the protection scope of the present invention.
It is to be noted that unless otherwise defined, technical or scientific terms used herein should be taken in a general sense as understood by one of ordinary skill in the art to which the present application belongs. If, throughout, reference is made to "first," "second," etc., the description of "first," "second," etc., is used merely for distinguishing between similar objects and not for understanding as indicating or implying a relative importance, order, or implicitly indicating the number of technical features indicated, it being understood that the data of "first," "second," etc., may be interchanged where appropriate.
In the related art, for a split control rod assembly, typically, the moving body is replaced every 1 year, and the outer sleeve is replaced every 1.5 years. The related art method for replacing the moving body and the outer sleeve generally replaces the moving body alone or replaces the outer sleeve alone.
In the related art, the moving body and the outer sleeve have respective refueling processes. In the process of refueling a moving body or an outer sleeve, a new outer sleeve (or a new moving body) needs to be carried into the reactor core by using a special tool for refueling (or a special sleeve for refueling), and then a spent outer sleeve (or a spent moving body) needs to be carried out of the reactor. Specifically, the special tool for material changing can be locked or unlocked with the outer sleeve in the outer sleeve; in the reactor core, the operation head of the special tool for grabbing and changing the materials can be used for driving the special tool for changing the materials to move through the material changing machine of the material changing system in the reactor core, so that the outer sleeve is driven to move. In addition, in the reactor core, the special refueling tool and the outer sleeve can be locked or unlocked through the operation of the refueling machine of the in-reactor refueling system, so that after the new outer sleeve is placed in the core working position, the new outer sleeve and the special refueling tool can be unlocked, then the special refueling tool and the spent outer sleeve are locked, and then the spent outer sleeve is carried out of the core by the special refueling tool.
Accordingly, the mobile body can be locked or unlocked with the reload-dedicated sleeve within the reload-dedicated sleeve. In the reactor, the operation head of the moving body can be grabbed by a refueling machine of the in-reactor refueling system to drive the moving body to move, so that the special sleeve for refueling is driven to move. In addition, in the reactor, the locking or unlocking of the moving body and the special sleeve for reloading can be realized through the single use of a reloading machine of a reloading system in the reactor or the cooperation of the reloading machine and a cock, so that the new moving body and the special sleeve for reloading can be unlocked, the new moving body can be put into the outer sleeve of the reactor core, the spent moving body and the special sleeve for reloading are locked, and the spent moving body is utilized to carry the special sleeve for reloading out of the reactor core.
Due to equipment in the in-stack and out-of-stack refueling systems such as: the loading and unloading hoist, the equipment such as spent subassembly conversion bucket are used for receiving spent fuel subassembly or spent outer sleeve, and independent reload specialized tool lacks the interface size with above-mentioned equipment, therefore independent reload specialized tool can not transport out the reactor core, reload specialized tool must with outer sleeve or temporary storage sleeve locking, overall dimension is complete just can transport out the reactor core. Therefore, the problem of removal of the refueling tool from the reactor must be considered when designing replacement of the outer sleeve.
In the related art, for such a refueling process, at the time of initial installation of a reactor core, it is necessary to manually place a control rod assembly model at a reactor core working site, the control rod assembly model including a moving body model having the same shape as the moving body but not having neutron absorbing material disposed therein, and an outer sleeve model; the shape of the outer sleeve model is the same as the outer sleeve. After the reactor core is installed, the new outer sleeve is replaced by a special tool for changing the materials through the matching of a material changing machine of a material changing system in the reactor and a cock, and the new moving body is replaced by a special sleeve for changing the materials, so that the installation of the control rod assembly is completed.
While the reactor is running, the moving body and the outer sleeve need to be replaced at the same time every few years (e.g., 3 years), and the efficiency of replacing the moving body or the outer sleeve separately is too low in the related art.
In addition, when the reactor is retired, all control rod assemblies need to be removed from the reactor. In the related art, all control rod assemblies can be replaced by only replacing the control rod assembly model with "new" and "old".
As can be seen, in the related art, when the control rod assembly is first installed in the reactor core, when the moving body and the outer sleeve are simultaneously replaced, or when the reactor is retired, the moving body or the outer sleeve needs to be separately installed (or removed), and only the "new" and "old" refueling mode can be adopted, and obviously, the refueling efficiency of such a refueling process is too low.
The present invention thus provides a new method of replacing a split control rod assembly in which, in particular, a tool dedicated to reloading and a sleeve dedicated to reloading are arranged such that the tool dedicated to reloading is locked or unlocked within the sleeve dedicated to reloading. For example, the structure of the special sleeve for changing the materials in the related art can be improved, so that the special sleeve for changing the materials has a locking structure similar to that of the outer sleeve, and the special tool for changing the materials can be locked and unlocked. Therefore, the invention can realize that the moving-out of the spent moving body (or the spent outer sleeve) and the putting-in process of the new moving body (the new outer sleeve) are carried out separately, and when the spent control rod assembly is moved out, the special tool for material changing is utilized to carry the special sleeve for material changing into the reactor, and the special sleeve for material changing is respectively carried by the outer sleeve and the spent moving body to go out of the reactor; when a new control rod assembly is installed, the special refueling tool and the special refueling sleeve respectively carry a new outer sleeve and a new moving body into the reactor core, and then the special refueling tool carries the special refueling sleeve out of the reactor. Therefore, the invention can move out (or mount) the moving body and the outer sleeve of the control rod assembly at the same time, thereby improving the replacement efficiency of the split control rod assembly.
In the embodiment of the invention, the special tool for material changing can be inserted into the outer sleeve, and the special tool and the outer sleeve can be mutually locked (or locked) and unlocked; the movable body can be inserted into the sleeve special for material changing, and the movable body and the sleeve can be mutually locked (or locked) and unlocked. When the special tool for changing the fuel is locked with the outer sleeve, the external structure of the special tool for changing the fuel is similar to that of the fuel assembly; when the special sleeve for changing the materials is locked with the movable body, the external structure of the special sleeve for changing the materials is similar to the external structure of the fuel assembly, and the special sleeve for changing the materials can be compatible with all relevant equipment in the existing material changing system. Meanwhile, the special tool for changing the fuel can be inserted into the special sleeve for changing the fuel, and the special tool for changing the fuel can be mutually locked (or locked) and unlocked, and when the special tool for changing the fuel is locked, the special tool for changing the fuel is similar to the external structure of the fuel assembly, and can also be compatible with related equipment in the existing fuel changing system.
Fig. 1 is a schematic structural view of a refueling tool according to an embodiment of the present application. Referring to fig. 1, a tool 100 for controlling the reloading of an outer sleeve of a stick assembly may comprise: the device comprises an operating head 110, a sleeve assembly 120 fixedly connected with the operating head 110 and a bottom structure 130.
The shape of the operating head 110 may be similar to the shape of the operating head of a fuel rod in order to accommodate the entire refueling system, e.g., a new component loader, a transfer machine, a gripping glove of a refueling machine, a pool operating machine, etc., may grip the operating head 110 of the refueling special purpose tool 100.
The operating head 110 may include a head 111, a shoulder 113, and a connection 112 connecting the head 111 and the shoulder 113. The head 111 and the shoulder 113 of the operation head 110 each include a truncated cone portion with a gradually expanding diameter, a cylindrical portion with a uniform diameter, and an inverted cone portion with a gradually decreasing diameter in this order. The connecting portion 112 is a cylindrical portion having a uniform diameter.
The shoulder 113 of the operating head 110 is provided with a plurality of limit projections 1131 in the circumferential direction for cooperating with a plurality of vertical slots on the gripping glove of the in-reactor refueling system. When the operating head 110 is gripped by the gripping glove, the gripping glove acts on the shoulder 113 of the operating head 110, a vertical groove with an opening at the lower part is formed in the gripping glove, and the limit protrusion 1131 of the operating head 110 is positioned in the vertical groove, so that the gripping glove can drive the special tool 100 for changing materials to rotate.
FIG. 2 is a cross-sectional view of the engagement between the glove, small grid header, locked reload tool and outer sleeve. Referring to fig. 2, outer sleeve 200 is inserted through its prongs 25 into the cartridge (i.e., core operating position) of small grid header 300. Sleeve assembly 120 and bottom structure 130 of tool 100 are positioned inside outer sleeve 200.
Spring 24 and locking sleeve 23 are disposed within pin 25 of outer sleeve 200. The locking sleeve 23 is axially slidable up and down, and a spring 24 is used to provide an upward abutment force to the locking sleeve 23.
A recess is formed in the locking sleeve 23 and the bottom structure 130 extends into the recess. The grooves of locking sleeve 23 and the cross section of bottom structure 130 are hexagonal so that locking sleeve 23 can rotate about an axis with the special tool for changing material 100 under the action of glove 400 (at this time, outer sleeve 200 remains stationary with respect to small grid header 300 and locking sleeve 23 rotates with respect to small grid header 300).
The bottom structure 130 is circumferentially provided with a plurality of bosses 131. A plurality of bosses 21 are provided in outer sleeve 200, and a slot 22 is formed between two adjacent bosses 21. When the tool 100 is rotated about an axis by the glove 400, the boss 131 of the bottom structure 130 may be located below the boss 21 or below the slot 22.
After the tool 100 rotates about the axis by a predetermined angle under the action of the grip sleeve 400, if the boss 131 of the bottom structure 130 is located under the boss 21, the grip sleeve 400 moves upward, and the tool 100 moves upward under the action of the spring 24, so that the upper surface of the boss 131 of the tool 100 abuts against the boss 21 of the outer sleeve 200, and the tool 100 is locked with the outer sleeve 200 inside the outer sleeve 200.
After tool 100 rotates about the axis by a predetermined angle under the action of grip sleeve 400, tool 100 is unlocked from outer sleeve 200 within outer sleeve 200 if boss 131 of bottom structure 130 is positioned below slot 22 (as shown in fig. 3). At this time, grip sleeve 400 may move special tool 100 upward away from outer sleeve 200.
The peripheral wall of the locking sleeve 23 is provided with a pin which can be locked or unlocked with a limit groove provided on the small louver header 300 when the locking sleeve 23 rotates around the axis together with the tool 100 for reloading under the action of the glove 400.
Fig. 4 is a schematic structural view of a cartridge dedicated to use in a reload according to an embodiment of the application. Fig. 5 is a sectional view taken along the direction B-B in fig. 4. Referring to fig. 4 and 5, the reload-dedicated sleeve 500 includes a main tube body 52, a pin 53, a moving body locking structure 51, and a reload tool locking structure.
The main pipe body 52 has a housing chamber formed therein for housing the moving body 600 of the control rod assembly. Pins 53 are fixedly connected to the lower ends of main tubes 52 and support main tubes 52, pins 53 being insertable into a small grid header 300 of the core.
FIG. 6 is a mating view of the glove, small grid header, locked reload sleeve and mobile body; fig. 7 is a sectional view taken along the direction C-C in fig. 6, and fig. 8 is a partially enlarged view of the region D in fig. 6. Referring to fig. 4 to 8, the moving body locking structure 51 is used to cooperate with the annular groove 601 on the operation head 610 of the moving body 600 to lock or unlock the moving body 600 with the reload-dedicated sleeve 500.
In the illustrated embodiment, the mobile locking structure 51 includes a first tube 511, a movable sleeve 512, and a spring 513.
The lower end of the first pipe body 511 is fixedly connected with the main pipe body 52, and a plurality of balls 5111 capable of moving along the radial direction are arranged on the pipe wall of the first pipe body 511 along the circumferential direction. The movable sleeve 512 is movably sleeved on the first pipe body 511. The upper end of the movable sleeve 512 is extended upward to form a protrusion 5121. By the cooperation of the protrusions 5121 and the vertical grooves of the grip sleeve 400, the circumferential positioning of both the movable sleeve 512 and the grip sleeve 400 is achieved, so that when the grip sleeve 400 drives the moving body 600 to rotate, the movable sleeve 512 also rotates around the axis at the same time.
The movable sleeve 512 is recessed circumferentially to form a plurality of receiving grooves (not shown), and the balls 5111 are movable radially inward to the locking position or radially outward to the unlocking position when the movable sleeve 512 is rotated about the axis relative to the first tube 511. In the locking position, the balls 5111 are engaged with the annular groove 601 of the moving body 600, thereby locking the cartridge 500 for reloading with the moving body 600. In the unlocking position, the balls 5111 are separated from the annular groove 601 of the moving body 600, thereby unlocking the reload-dedicated sleeve 500 from the moving body 600.
Specifically, when the balls 5111 are staggered from the receiving groove of the movable sleeve 512 during the process of the gripper sleeve 400 driving the movable sleeve 512 to rotate, the balls 5111 move radially inwards to the locking position under the action of the wall of the movable sleeve 512. If the balls 5111 face the receiving groove of the movable sleeve 512, the balls 5111 are allowed to move radially outward to the unlocking position.
A spring 513 is fitted over the first tube 511 for providing an axially upward abutment force to the movable sleeve 512 to hold the movable sleeve 512 in an upper position of the first tube 511. The spring 513 may be, for example, a compression spring.
The tool lock includes a plurality of bosses extending radially inward from the inner wall of the main tubular body 52 with slots formed between adjacent bosses. The tool lock structure is similar to the lock structure of the outer sleeve and will not be described in detail herein.
Since the reloading tool locking structure is similar to the locking structure of the outer sleeve, the reloading tool can be locked or unlocked with the dedicated sleeve by means of the reloading tool locking structure.
In the method of an embodiment of the present invention, two vacancies may be reserved at the reactor core storage well (i.e., the small grid header): the first reserved empty space and the second reserved empty space are completely emptied, the first reserved empty space presets an outer sleeve as a temporary storage sleeve, and the replacement operation of the control rod assembly in the reactor core is realized through the arrangement.
Since the removal of the spent moving body (or spent outer sleeve) is separate from the insertion of the new moving body (new outer sleeve), and the moving body and outer sleeve of the control rod assembly can be removed or installed at the same time. Thus, the replacement method of the present invention can be further extended to a method of installing a control rod assembly within a reactor core and a method of removing a control rod assembly from a reactor core. Therefore, when the control rod assembly is installed for the first time in the reactor core, a control rod assembly model is not required to be placed at the working position of the reactor core manually, and a new control rod assembly can be installed into the working position of the reactor core after the installation of the reactor core is completed; and, the spent control rod assembly can be completely swapped out of the reactor when the reactor is retired, without the need for replacement with a control rod assembly model.
Fig. 9 is a flowchart of a method for installing a control rod assembly in a reactor core according to an embodiment of the present invention, and referring to fig. 9, a method for installing a control rod assembly in a reactor core (hereinafter, simply referred to as an installation method) according to an embodiment of the present invention includes steps S100 to S108.
Step S100, providing a special tool for changing materials, wherein the special tool for changing materials can be locked or unlocked with the outer sleeve in the outer sleeve;
step S102, locking the special tool for changing materials with the outer sleeve;
Step S104, placing the locked special tool for refueling and the outer sleeve at a reactor core working position in the reactor core;
Step S106, unlocking the special tool for changing the materials and the outer sleeve; and
Step S108, removing the special tool for changing materials from the outer sleeve.
In step S100, a reloading tool is provided as shown in fig. 1, which reloading tool can be locked or unlocked with the outer sleeve inside the outer sleeve.
In step S102, the refueling tool may be locked with the outer sleeve within a fresh fuel silo. The installation method further comprises the following steps: transporting the locked special tool for changing materials and the outer sleeve into a reactor hall; and then the locked special refueling tool and the outer sleeve are conveyed into the reactor core through the in-and-out-of-reactor refueling system.
In step S104, in the reactor, the operation head of the refueling special tool is grasped by the refueling machine of the in-reactor refueling system, and the locked refueling special tool and the outer sleeve are placed at a core working position in the reactor core. Those skilled in the art will readily appreciate that in the present application, when installing control rod assemblies in the reactor core, there are a plurality of core sites within the core for installing control rod assemblies. The installation process may be when the control rod assembly is first installed in the reactor core or when the control rod assembly is replaced. When the control rod assemblies are replaced, both the spent mobile and the spent outer sleeve of at least one control rod assembly have been moved out of the core to leave at least one core operational site at the core for installation of new outer sleeve and new mobile.
In step S106, after the locked refueling special tool and the outer sleeve are placed at the core working position within the reactor core, the refueling special tool and the outer sleeve may be unlocked by the cooperation of the refueling machine and the tap of the in-core refueling system, and the outer sleeve and the small grid header are locked while the refueling special tool and the outer sleeve are unlocked.
In step S108, the unlocked reload specific tool is removed from the outer sleeve by means of a reloader of the in-stack reload system.
Through steps S100 to S108, an outer sleeve of a control rod assembly is installed at a core operating site within the reactor core.
In some embodiments, a first reserved space is reserved in the reactor core, and a temporary storage sleeve for temporarily storing the special tool for material changing is arranged in the first reserved space. It is easy to understand that the core vacancy is a core vacancy on the small grid header, and is specially used for placing the temporary storage sleeve. In some embodiments, the location of the first reserved void remains unchanged, i.e., one core void fixed on the small grid header is used to place the temporary storage sleeve.
In such an embodiment, after step S108, the installation method may further include step S110, transferring the tool dedicated to material change into the temporary storage sleeve.
In some embodiments, the reactor core is reserved with a second reserved void, which is also one core void on the small grid header. In some embodiments, the location of the second reserved void remains unchanged, i.e., one core void fixed on the small grid header is used as the second reserved void.
In some embodiments, referring to fig. 10, the installation method may further include steps S112 to S120 after step S108 or after step S110 to place the moving body inside the outer sleeve.
Step S112, providing a sleeve special for material replacement, wherein the movable body can be locked or unlocked with the sleeve special for material replacement in the sleeve special for material replacement;
step S114, locking the movable body and the sleeve special for material changing;
step S116, placing the locked moving body and the special sleeve for changing materials at the second reserved vacancy;
step S118 of unlocking the mobile body and the special sleeve for refueling;
and step S120, transferring the moving body into the outer sleeve.
Through steps S100 to S120, the outer sleeve is placed at the reactor core working position, and the moving body is placed in the outer sleeve, so that the installation of a group of control rod assemblies is completed.
In step S112, a cartridge dedicated to the reloading is provided, as shown in fig. 4, and the movable body can be locked or unlocked with the cartridge dedicated to the reloading within the cartridge dedicated to the reloading.
In step S114, the mobile body may be locked with the cartridge for refueling in a new fuel storage. The mounting method further comprises the following steps: transporting the locked moving body and the special sleeve for reloading into a reactor hall; and then the locked moving body and the special sleeve for refueling are conveyed into the reactor core through the in-and-out refueling system.
In step S116, the locked mobile body and the refueling special sleeve are placed in the reactor core at a second reserved space by the operation head of the mobile body being grasped by the refueling machine of the in-reactor refueling system.
In step S118, after the locked mobile body and the reload dedicated sleeve are placed in the second reserved space, the mobile body and the reload dedicated sleeve may be unlocked by the cooperation of the reload machine and the cock of the in-stack reload system.
In step S120, the unlocked mobile body is transferred to the outer sleeve by the in-stack refueling machine of the in-stack refueling system.
In some embodiments, the reload specific tool is arranged to be lockable or unlockable within the reload specific sleeve.
In such an embodiment, referring to fig. 10, after step S120, the installation method may further include step S122 and step S124 to remove the refueling special purpose tool and the refueling special purpose sleeve from the reactor.
Step S122, transferring the special tool for changing the materials into the special sleeve for changing the materials, and locking the special sleeve for changing the materials;
step S124, removing the locked refueling special tool and the refueling special sleeve from the reactor.
In step S122, after transferring the tool-specific for reloading into the cartridge-specific for reloading, the tool-specific for reloading may be locked with the cartridge-specific for reloading by means of the cooperation of the reloading machine and the tap of the in-pile reloading system.
In step S124, the locked reload tool and reload sleeve may be transported to the outside of the reactor by means of a loading and unloading elevator.
It will be appreciated by those skilled in the art that the transfer of the refueling tool and the mobile body, as well as the unlocking of the refueling tool and the outer sleeve, the unlocking of the mobile body and the refueling sleeve, and the locking of the refueling tool and the refueling sleeve may be accomplished by the cooperation of a refueling machine and a tap of the in-reactor refueling system within the reactor.
In some embodiments, the temporary storage sleeve may be of the same construction as the outer sleeve.
In some embodiments, prior to placing the locked refueling special tool and the outer sleeve at a core operational location within the reactor core, the installation method further comprises: locking the special tool for changing the materials with the temporary storage sleeve outside the reactor; placing the locked refueling special tool and the temporary storage sleeve at a first reserved vacancy in the reactor core; unlocking the special tool for changing the materials and the temporary storage sleeve; and removing the special tool for replacing the materials from the temporary storage sleeve. That is, a temporary storage sleeve may be placed at the first reserved void in advance prior to installation of the control rod assembly in the core.
In some embodiments, the refueling tool may be locked with the temporary storage sleeve within a fresh fuel silo; the mounting method further comprises the following steps: transporting the locked special tool for changing materials and the temporary storage sleeve into a reactor hall; and transporting the locked refueling special tool and the temporary storage sleeve into the reactor core.
Of course, in some embodiments, the temporary storage sleeve may also be manually placed at the time of initial installation of the control rod assembly in the reactor core (i.e., prior to the reactor seal being charged with sodium).
FIG. 11 illustrates the change in core during installation of control rod assemblies within the reactor core.
The initial state of the reactor core is shown in fig. 11a. The reactor core is provided with a core working position 30, a first reserved vacancy 31 and a second reserved vacancy 32, wherein a temporary storage sleeve 4 is arranged in the first reserved vacancy 31.
Specifically, the process of installing the control rod assembly includes:
(1) The locked refueling special tool 6 and the new outer sleeve 7 are put at a reactor core working position 30 (see fig. 11 b) in the reactor core through the cooperation operation of the cock and the refueling machine;
(2) Unlocking the special tool for changing material 6 from the new outer sleeve 7 and transferring the special tool for changing material 6 into the temporary storage sleeve 4 positioned in the first reserved empty space 31 through the cooperation operation of the cock and the material changing machine, and then the new outer sleeve 7 is emptied (see fig. 11 c);
(3) The locked cartridge 5 dedicated to reloading and the new mobile body 8 are put into the second reserved space 32 by the cooperation of the cock and the reloading machine (see fig. 11 d);
(4) Unlocking the new moving body 8 from the cartridge 5 dedicated to the reloading by the operation of the reloading machine, and placing the new moving body 8 inside the new outer sleeve 7, the new control rod assembly completing the loading operation (see fig. 11 e);
(5) By the cooperation of the tap and the reloading machine, the reloading tool 6 in the temporary storage sleeve 4 is put into the reloading sleeve 5 in the second reserved space 32 (see fig. 11 f), and the two are locked and carried out of the reactor (see fig. 11g, i.e. the state of the reactor core with a set of new control rod assemblies).
The embodiment of the invention also provides a method for taking the control rod assembly out of the reactor core. The reactor core is reserved with a first reserved vacancy and a second reserved vacancy, wherein a temporary storage sleeve for temporarily storing a special tool for material replacement is arranged in the first reserved vacancy.
FIG. 12 is a flow chart of a method of removing a control rod assembly from a reactor core in accordance with one embodiment of the invention. Referring to fig. 12, a method of extracting a control rod assembly from a reactor core (hereinafter, referred to as an extraction method) includes steps S200 to S212.
Step 200, providing a sleeve special for material replacement, wherein the movable body can be locked or unlocked with the sleeve special for material replacement in the sleeve special for material replacement; providing a reloading special tool which can be locked or unlocked with the outer sleeve and the reloading special sleeve respectively in the outer sleeve and the reloading special sleeve;
step S202, locking the special tool for changing materials and the special sleeve for changing materials;
Step S204, placing the locked special tool for changing the materials and the special sleeve for changing the materials at the second reserved vacancy in the reactor core;
Step S206, transferring the moving body into the temporary storage sleeve;
Step S208, unlocking the special tool for changing materials and the special sleeve for changing materials;
step S210, transferring the special tool for material changing into the outer sleeve to be locked with the outer sleeve;
step S212, the locked special tool for changing the materials and the outer sleeve are moved out of the reactor.
Through steps S200 to S212, the outer sleeve is moved out of the core.
In step S200, a reloading tool is provided as shown in fig. 1, which reloading tool can be locked or unlocked with the outer sleeve inside the outer sleeve. As shown in fig. 4, the provided special sleeve for changing the material can be locked or unlocked with the special sleeve for changing the material in the special sleeve for changing the material.
In step S202, locking the refueling special tool with the refueling special sleeve in a new fuel storage; the extraction method further comprises the step of conveying the locked special tool for changing and the special sleeve for changing into a reactor hall; and transporting the locked refueling special tool and the refueling special sleeve into the reactor core.
In some embodiments, after unlocking the reload specific tool from the reload specific sleeve further comprises: transferring the moving body into the cartridge dedicated to the reloading to be locked with the cartridge dedicated to the reloading; and moving the locked moving body and the special sleeve for material changing out of the reactor. Thereby, the moving body is moved out of the core.
In the reactor, the transfer of the special tool for changing the materials and the moving body, the unlocking of the special tool for changing the materials and the special sleeve for changing the materials, the locking of the special tool for changing the materials and the outer sleeve, and the locking of the moving body and the special sleeve for changing the materials are realized through the matching of a material changing machine and a cock of a material changing system in the reactor.
In some embodiments, the retrieval method further comprises: locking the special refueling tool with the temporary storage sleeve outside the reactor, and placing the locked special refueling tool and temporary storage sleeve at the first reserved vacancy in the reactor core; unlocking the special tool for changing the materials and the temporary storage sleeve; and removing the special tool for replacing the materials from the temporary storage sleeve. That is, a temporary storage sleeve may be placed at the first reserved void in advance.
Of course, in some embodiments, the temporary storage sleeve may also be manually placed at the time of initial installation of the control rod assembly in the reactor core (i.e., prior to the reactor seal being charged with sodium).
FIG. 13 illustrates the change in core vacancy during the removal of a control rod assembly from the reactor core.
The initial state of the reactor core is shown in fig. 13a. The reactor core is provided with a first reserved vacancy 31 and a second reserved vacancy 32, and a temporary storage sleeve 4 is arranged in the first reserved vacancy 31.
Specifically, the process of removing the control rod assembly includes:
(1) Transferring the locked refueling tool 6 and the refueling sleeve 5 to a second reserved space 32 in the core by the cooperation of the refueling machine of the in-stack refueling system and the cock (see fig. 13 b);
(2) The movable body 2 of the spent control rod assembly to be replaced in the reactor core is transferred into the temporary storage sleeve 4 at the first reserved empty space 31 by matching the refueling machine with the cock, and the outer sleeve 1 of the spent control rod assembly to be replaced is emptied (see fig. 13 c);
(3) Unlocking the special refueling tool 6 locked at the second reserved space 32 from the special refueling sleeve 5 through the operation of the refueling machine, transferring the special refueling tool 6 into the empty spent outer sleeve 1 in the reactor core, and locking the special refueling tool 6 with the spent outer sleeve 1 (see fig. 13 d);
(4) The movable body is drawn out from the temporary storage sleeve 4 at the first reserved vacancy 31 to be transferred into the special sleeve 5 for changing the material at the second reserved vacancy 32 by matching the material changing machine with the cock, and the movable body 2 is locked with the special sleeve 5 for changing the material (see fig. 13 e);
(5) The locked sleeve 5 and spent moving body 2, tool 6 and outer sleeve 1 are transported out of the reactor (see fig. 13 f).
Aiming at the condition that the moving body and the outer sleeve reach the refueling cycle at the same time, the embodiment of the invention also provides a method for replacing the control rod assembly. The reactor core is reserved with a first reserved vacancy and a second reserved vacancy, wherein a temporary storage sleeve for temporarily storing a special tool for material replacement is arranged in the first reserved vacancy.
FIG. 14 is a flow chart of a method of replacing a control rod assembly according to one embodiment of the present invention. Referring to fig. 14, the replacement method includes steps S300 to S308.
Step S300, providing a sleeve special for material changing and a tool special for material changing;
step S302, removing the special tool for changing the materials and the spent outer sleeve from the reactor core vacancy;
Step S304, removing the spent moving body and the special sleeve for material changing from the second reserved vacancy to the reactor;
step S306, moving the new outer sleeve into the core working position of the reactor core;
step S308, the new moving body is moved into the new outer sleeve.
In steps S302 and S304, the refueling special tool and the spent outer sleeve are removed from the reactor and the spent mobile and the refueling special sleeve are removed from the reactor using the aforementioned removal method.
In steps S306 and S308, the new outer sleeve is moved into the core working position of the reactor core by the aforementioned installation method, and the new mobile body is moved into the new outer sleeve.
A detailed description of a refueling process for a split change control rod assembly according to the present invention is provided below with reference to fig. 11 and 13.
1. In a new fuel warehouse, firstly locking a special refueling tool and a special refueling sleeve, and then conveying the locked special refueling tool and the locked special refueling sleeve into a reactor hall through a new component process conveying route in the existing component refueling process route;
2. After the two materials are transported to a reactor hall, the locked special refueling tool and the special refueling sleeve are transported to the reactor core through the external and internal refueling process routes in the existing component refueling process route;
3. Within the reactor core:
The initial state of the reactor core is shown in fig. 13a. The reactor core is provided with a first reserved vacancy 31 and a second reserved vacancy 32, and a temporary storage sleeve 4 is arranged in the first reserved vacancy 31.
(1) Transferring the locked refueling tool 6 and the refueling sleeve 5 to a second reserved space 32 in the core by the cooperation of the refueling machine of the in-stack refueling system and the cock (see fig. 13 b);
(2) The movable body 2 of the spent control rod assembly to be replaced in the reactor core is transferred into the temporary storage sleeve 4 at the first reserved empty space 31 by matching the refueling machine with the cock, and the outer sleeve 1 of the spent control rod assembly to be replaced is emptied (see fig. 13 c);
(3) Unlocking the special refueling tool 6 locked at the second reserved space 32 from the special refueling sleeve 5 through the operation of the refueling machine, transferring the special refueling tool 6 into the empty spent outer sleeve 1 in the reactor core, and locking the special refueling tool 6 with the spent outer sleeve 1 (see fig. 13 d);
(4) The movable body 2 is drawn out from the temporary storage sleeve 4 at the first reserved vacancy 31 to be transferred into the special sleeve 5 for changing the material at the second reserved vacancy 32 by matching the material changing machine with the cock, and the movable body 2 is locked with the special sleeve 5 for changing the material (see fig. 13 e);
(5) The locked sleeve 5 and spent moving body 2, tool 6 and outer sleeve 1 are transported out of the reactor (see fig. 13 f).
4. The spent moving body 2 and the special sleeve 5 for changing the materials, the spent sleeve 1 and the special tool 6 for changing the materials are transported to a spent fuel pool for storage through a spent assembly process transportation route in the existing assembly material changing process route;
5. in a new fuel warehouse, locking a special tool for changing materials with a new outer sleeve, a new moving body and a special sleeve for changing materials, and then transporting the special tool for changing materials into a reactor hall through a new component process transportation route in the existing component material changing process route;
6. After the two materials are transported to a reactor hall, the locked special refueling tool, a new outer sleeve, a new moving body and a special refueling sleeve are transported to a reactor core through the external and internal refueling process routes in the existing component refueling process route;
7. Within the reactor core:
(1) The locked refueling special tool 6 and the new outer sleeve 7 are put at a reactor core working position 30 (see fig. 11 b) in the reactor core through the cooperation of the cock and the refueling machine;
(2) Unlocking the special tool for changing material 6 from the new outer sleeve 7 by the operation of the cock and the material changing machine and transferring the special tool for changing material 6 into the temporary storage sleeve 4 positioned in the first reserved empty space 31, and leaving the new outer sleeve 7 empty (see fig. 11 c);
(3) The locked cartridge 5 dedicated to reloading and the new mobile body 8 are put into the second reserved space 32 by the cooperation of the cock and the reloading machine (see fig. 11 d);
(4) Unlocking the new moving body 8 from the cartridge 5 dedicated to the reloading by the operation of the reloading machine, and placing the new moving body 8 inside the new outer sleeve 7, the new control rod assembly completing the loading operation (see fig. 11 e);
(5) By operating the tap and the reloader, the reloading tool 6 in the temporary storage sleeve 4 is placed in the reloading sleeve 5 in the second reserved space 32 (see fig. 11 f) and both are locked out of the reactor (see fig. 11g, i.e. the state of the reactor core with a new set of control rod assemblies).
8. And (3) conveying the special tool for refueling, which is conveyed out of the reactor core, into a spent fuel pool for storage through a spent component process conveying route in the existing component refueling process route.
It can be seen that the embodiments of the present invention have at least the following beneficial effects:
(1) The replacement operation of the control rod assembly can be realized under the operation of the existing equipment of the refueling system;
(2) The refueling process flow does not affect the refueling operation of the fuel assembly;
(3) The replacement efficiency of the split control rod assembly can be improved through the process flow of the material changing process;
(4) The spent control rod assembly can be completely swapped out of the reactor when the reactor is retired through the refueling process flow;
(5) The new control rod assembly can be loaded into the reactor core when the spent control rod assembly is completely swapped out of the reactor core through the refueling process flow.
It should also be noted that, in the embodiments of the present invention, the features of the embodiments of the present invention and the features of the embodiments of the present invention may be combined with each other to obtain new embodiments without conflict.
The present invention is not limited to the above embodiments, but the scope of the invention is defined by the claims.
Claims (12)
1. A method of installing a control rod assembly within a reactor core, the control rod assembly including a moving body and an outer sleeve, the method comprising:
Providing a reloading special tool which can be locked or unlocked with the outer sleeve in the outer sleeve;
Locking the refueling special tool with the outer sleeve outside the reactor;
Placing the locked refueling special tool and the outer sleeve at a core working position in the reactor;
unlocking the special tool for changing the materials and the outer sleeve; and
Removing the refueling special purpose tool from within the outer sleeve;
A first reserved vacancy is reserved in the reactor core, and a temporary storage sleeve for temporarily storing the special tool for material changing is arranged in the first reserved vacancy; the method further includes, after removing the refueling special purpose tool from within the outer sleeve: transferring the special tool for changing materials into the temporary storage sleeve; the reactor core is reserved with a second reserved void,
The method further includes, after removing the refueling special purpose tool from within the outer sleeve: providing a sleeve special for material changing, wherein the movable body can be locked or unlocked with the sleeve special for material changing in the sleeve special for material changing; locking the mobile body and the special sleeve for material changing outside the reactor; placing the locked mobile body and the refueling special sleeve at a second reserved vacancy of the reactor core; unlocking the moving body and the special sleeve for reloading; and transferring the mobile body into the outer sleeve;
the special tool for changing the materials can be locked or unlocked with the special sleeve for changing the materials in the special sleeve for changing the materials; the method further includes, after unlocking the mobile body from the reload-dedicated sleeve: transferring the special tool for changing the materials into the special sleeve for changing the materials, and locking the special tool for changing the materials with the special sleeve for changing the materials; and removing the locked refueling special tool and the refueling special sleeve from the reactor;
The special sleeve for changing the materials comprises a main pipe body, a pin, a moving body locking structure and a changing tool locking structure, wherein a containing cavity is formed in the main pipe body and used for containing the moving body; the pins are fixedly connected with the lower end of the main pipe body;
the movable body locking structure comprises a first pipe body, a movable sleeve and a spring, wherein the lower end of the first pipe body is fixedly connected with the main pipe body, a plurality of balls capable of moving along the radial direction are arranged on the pipe wall of the first pipe body along the circumferential direction, and the movable sleeve is movably sleeved on the first pipe body; the movable sleeve is sunk inwards along the circumferential direction to form a plurality of accommodating grooves, and when the movable sleeve rotates around the axis relative to the first pipe body, the balls can move inwards to a locking position or outwards to an unlocking position along the radial direction; in the locking position, the balls are matched with the annular groove of the moving body, so that the special sleeve for changing the materials is locked with the moving body; in the unlocking position, the ball is separated from the annular groove of the moving body, so that the special sleeve for changing the materials is unlocked from the moving body;
The spring is sleeved on the first pipe body and is used for providing an axial upward abutting force for the movable sleeve so as to keep the movable sleeve at the upper position of the first pipe body;
The special tool for changing the materials can be locked or unlocked with the sleeve barrel for changing the materials through the locking structure of the tool for changing the materials.
2. The method of claim 1, wherein the step of determining the position of the substrate comprises,
In the reactor, the transfer of the special tool for changing the materials and the moving body, the unlocking of the special tool for changing the materials and the outer sleeve, the unlocking of the moving body and the special sleeve for changing the materials and the locking of the special tool for changing the materials and the special sleeve for changing the materials are realized through the matching of a material changing machine and a cock of a material changing system in the reactor.
3. The method of claim 1, wherein the step of determining the position of the substrate comprises,
The temporary storage sleeve has the same structure as the outer sleeve.
4. The method of claim 1, wherein said locking the refueling special tool with the outer sleeve outside the reactor comprises:
Locking the refueling special tool with the outer sleeve in a new fuel warehouse;
the method further comprises the steps of:
transporting the locked special tool for changing materials and the outer sleeve into a reactor hall; and
And conveying the locked special refueling tool and the outer sleeve into the reactor core.
5. The method of claim 1, wherein said locking the mobile body with the refueling special sleeve outside the reactor comprises:
Locking the mobile body and the sleeve special for changing materials in a new fuel warehouse;
the method further comprises the steps of:
transporting the locked moving body and the special sleeve for reloading into a reactor hall; and
And conveying the locked moving body and the special sleeve for refueling into the reactor core.
6. A method of removing a control rod assembly from a reactor core, the control rod assembly comprising a mobile body and an outer sleeve, characterized in that the reactor core is reserved with a first reserved void and a second reserved void, wherein a temporary storage sleeve for temporarily storing a refueling special purpose tool is arranged in the first reserved void; the method comprises the following steps:
Providing a sleeve special for material changing, wherein the movable body can be locked or unlocked with the sleeve special for material changing in the sleeve special for material changing;
providing a reloading special tool which can be locked or unlocked with the outer sleeve and the reloading special sleeve respectively in the outer sleeve and the reloading special sleeve;
locking the special tool for changing the materials with the sleeve for changing the materials outside the reactor;
Placing the locked refueling special tool and the refueling special sleeve at the second reserved void within the reactor core;
transferring the moving body into the temporary storage sleeve;
unlocking the special tool for changing the materials and the special sleeve for changing the materials;
transferring the special tool for material changing into the outer sleeve and locking the special tool with the outer sleeve; and
Removing the locked refueling special tool and the outer sleeve from the reactor;
The special sleeve for changing the materials comprises a main pipe body, a pin, a moving body locking structure and a changing tool locking structure, wherein a containing cavity is formed in the main pipe body and used for containing the moving body; the pins are fixedly connected with the lower end of the main pipe body;
the movable body locking structure comprises a first pipe body, a movable sleeve and a spring, wherein the lower end of the first pipe body is fixedly connected with the main pipe body, a plurality of balls capable of moving along the radial direction are arranged on the pipe wall of the first pipe body along the circumferential direction, and the movable sleeve is movably sleeved on the first pipe body; the movable sleeve is sunk inwards along the circumferential direction to form a plurality of accommodating grooves, and when the movable sleeve rotates around the axis relative to the first pipe body, the balls can move inwards to a locking position or outwards to an unlocking position along the radial direction; in the locking position, the balls are matched with the annular groove of the moving body, so that the special sleeve for changing the materials is locked with the moving body; in the unlocking position, the ball is separated from the annular groove of the moving body, so that the special sleeve for changing the materials is unlocked from the moving body;
The spring is sleeved on the first pipe body and is used for providing an axial upward abutting force for the movable sleeve so as to keep the movable sleeve at the upper position of the first pipe body;
The special tool for changing the materials can be locked or unlocked with the sleeve barrel for changing the materials through the locking structure of the tool for changing the materials.
7. The method of claim 6, further comprising, after unlocking the refueling special purpose tool from the refueling special purpose sleeve:
Transferring the moving body into the cartridge dedicated to the reloading to be locked with the cartridge dedicated to the reloading; and
And removing the locked moving body and the special sleeve for changing the materials from the reactor.
8. The method of claim 6, wherein the step of providing the first layer comprises,
The temporary storage sleeve has the same structure as the outer sleeve.
9. The method of claim 7, wherein the step of determining the position of the probe is performed,
In the reactor, the transfer of the special tool for changing the materials and the moving body, the unlocking of the special tool for changing the materials and the special sleeve for changing the materials, the locking of the special tool for changing the materials and the outer sleeve, and the locking of the moving body and the special sleeve for changing the materials are realized through the matching of a material changing machine and a cock of a material changing system in the reactor.
10. The method of claim 6, wherein said locking the refueling special tool with the refueling special sleeve outside the reactor comprises:
locking the refueling special tool with the refueling special sleeve in a new fuel warehouse;
the method further comprises the steps of:
Transporting the locked special tool for changing materials and the special sleeve for changing materials into a reactor hall; and
And conveying the locked special refueling tool and the special refueling sleeve into the reactor core.
11. A method of replacing a control rod assembly, the control rod assembly including a moving body and an outer sleeve, the method comprising:
Removing the refueling special tool and the spent outer sleeve from the reactor and removing the spent mobile and the refueling special sleeve from the reactor according to the method of claim 7;
The method of claim 1, moving a new outer sleeve into a core operational site of a reactor core, and moving a new mobile into the new outer sleeve.
12. The method of claim 11, wherein the step of determining the position of the probe is performed,
After all the spent outer sleeves and spent moving bodies of all the control rod assemblies are moved out of the reactor, the new outer sleeves and the new moving bodies are moved into the reactor core working position of the reactor core.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111129136.9A CN113871041B (en) | 2021-09-26 | 2021-09-26 | Method for installing, removing and replacing control rod assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111129136.9A CN113871041B (en) | 2021-09-26 | 2021-09-26 | Method for installing, removing and replacing control rod assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN113871041A CN113871041A (en) | 2021-12-31 |
| CN113871041B true CN113871041B (en) | 2024-05-10 |
Family
ID=78994418
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202111129136.9A Active CN113871041B (en) | 2021-09-26 | 2021-09-26 | Method for installing, removing and replacing control rod assembly |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113871041B (en) |
Citations (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB817265A (en) * | 1956-09-19 | 1959-07-29 | Westinghouse Electric Int Co | Improvements in or relating to nuclear reactors |
| US3494827A (en) * | 1967-10-10 | 1970-02-10 | Combustion Eng | Mechanical device for quickly disconnecting drive mechanism from control rod of nuclear reactor |
| US3773617A (en) * | 1970-12-22 | 1973-11-20 | Commissariat Energie Atomique | Control-rod assembly for nuclear reactors |
| GB1491552A (en) * | 1974-02-26 | 1977-11-09 | Kraftwerk Union Ag | Nuclear reactor |
| US4374801A (en) * | 1979-06-26 | 1983-02-22 | Framatome | Method of handling fuel assemblies and rods when reloading a nuclear reactor |
| US4637914A (en) * | 1984-01-30 | 1987-01-20 | Westinghouse Electric Corp. | Quick release guide sleeve assembly |
| EP0300745A2 (en) * | 1987-07-23 | 1989-01-25 | Mitsubishi Atomic Power Industries, Inc | Reactivity control method of light-water cooled, lightwater moderated nuclear reactor core and apparatus therefor |
| DE69108640D1 (en) * | 1990-08-17 | 1995-05-11 | Gen Electric | Centering device for use during the replacement of the fuel elements of water-cooled nuclear reactors. |
| JPH10132985A (en) * | 1996-10-31 | 1998-05-22 | Toshiba Corp | Method of replacing structure in reactor |
| JPH10142385A (en) * | 1996-11-13 | 1998-05-29 | Toshiba Corp | In-core maintenance work device |
| CN1308340A (en) * | 2000-02-08 | 2001-08-15 | 东芝株式会社 | Nuclear reactor cooling equipment and its operation method |
| TW476072B (en) * | 2000-10-30 | 2002-02-11 | Ohsono Katsunar | An absorbing rod, an apparatus for inserting the absorbing rod, a cask, and a method of storing spent fuel assemblies |
| CN103000237A (en) * | 2011-08-19 | 2013-03-27 | 巴布科克和威尔科克斯核能股份有限公司 | Nuclear reactor refueling methods and apparatuses |
| CN104919534A (en) * | 2013-01-15 | 2015-09-16 | 西屋电气有限责任公司 | Apparatus and method for removing the upper internals from a nuclear reactor pressurized vessel |
| CN105489255A (en) * | 2015-12-28 | 2016-04-13 | 中国原子能科学研究院 | Device and method for assembling fast reactor MOX components |
| CN112837832A (en) * | 2020-12-30 | 2021-05-25 | 中国原子能科学研究院 | Rotary type material changing special structure for replacing outer sleeve of control rod assembly |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3875374B2 (en) * | 1997-10-03 | 2007-01-31 | 株式会社東芝 | Extraction device for fast breeder reactor and its upper core mechanism |
| CN202373314U (en) * | 2011-10-25 | 2012-08-08 | 中国武汉核电运行技术股份有限公司 | Special tool for position enlarging of reactor core fuel subassembly |
| EP3753029B1 (en) * | 2018-02-12 | 2022-06-08 | Westinghouse Electric Company Llc | Thermal sleeve |
| CN109830310A (en) * | 2019-01-11 | 2019-05-31 | 中广核工程有限公司 | Ship reactor improved electric magnetic-type control rod drive mechanism |
| US11348700B2 (en) * | 2019-05-15 | 2022-05-31 | Ge-Hitachi Nuclear Energy Americas Llc | Boiling water reactor blade guide and exchange tool |
-
2021
- 2021-09-26 CN CN202111129136.9A patent/CN113871041B/en active Active
Patent Citations (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB817265A (en) * | 1956-09-19 | 1959-07-29 | Westinghouse Electric Int Co | Improvements in or relating to nuclear reactors |
| US3494827A (en) * | 1967-10-10 | 1970-02-10 | Combustion Eng | Mechanical device for quickly disconnecting drive mechanism from control rod of nuclear reactor |
| US3773617A (en) * | 1970-12-22 | 1973-11-20 | Commissariat Energie Atomique | Control-rod assembly for nuclear reactors |
| GB1491552A (en) * | 1974-02-26 | 1977-11-09 | Kraftwerk Union Ag | Nuclear reactor |
| US4374801A (en) * | 1979-06-26 | 1983-02-22 | Framatome | Method of handling fuel assemblies and rods when reloading a nuclear reactor |
| US4637914A (en) * | 1984-01-30 | 1987-01-20 | Westinghouse Electric Corp. | Quick release guide sleeve assembly |
| EP0300745A2 (en) * | 1987-07-23 | 1989-01-25 | Mitsubishi Atomic Power Industries, Inc | Reactivity control method of light-water cooled, lightwater moderated nuclear reactor core and apparatus therefor |
| DE69108640D1 (en) * | 1990-08-17 | 1995-05-11 | Gen Electric | Centering device for use during the replacement of the fuel elements of water-cooled nuclear reactors. |
| JPH10132985A (en) * | 1996-10-31 | 1998-05-22 | Toshiba Corp | Method of replacing structure in reactor |
| JPH10142385A (en) * | 1996-11-13 | 1998-05-29 | Toshiba Corp | In-core maintenance work device |
| CN1308340A (en) * | 2000-02-08 | 2001-08-15 | 东芝株式会社 | Nuclear reactor cooling equipment and its operation method |
| TW476072B (en) * | 2000-10-30 | 2002-02-11 | Ohsono Katsunar | An absorbing rod, an apparatus for inserting the absorbing rod, a cask, and a method of storing spent fuel assemblies |
| CN103000237A (en) * | 2011-08-19 | 2013-03-27 | 巴布科克和威尔科克斯核能股份有限公司 | Nuclear reactor refueling methods and apparatuses |
| CN104919534A (en) * | 2013-01-15 | 2015-09-16 | 西屋电气有限责任公司 | Apparatus and method for removing the upper internals from a nuclear reactor pressurized vessel |
| CN105489255A (en) * | 2015-12-28 | 2016-04-13 | 中国原子能科学研究院 | Device and method for assembling fast reactor MOX components |
| CN112837832A (en) * | 2020-12-30 | 2021-05-25 | 中国原子能科学研究院 | Rotary type material changing special structure for replacing outer sleeve of control rod assembly |
Non-Patent Citations (5)
| Title |
|---|
| CFR600堆芯组件自由跌落试验的冲击响应分析;苏喜平等;强度与环境;20210630;第48卷(第3期);第28-35页 * |
| The BWR hybrid 4 control rod;H.Gross;Nuclear Engineering and Design;19880831;第108卷(第3期);第 433-436页 * |
| 一种分体式控制棒组件换料工艺路线设计;王浩仲等;科技创新导报(第19期);第55-58页 * |
| 一种基于动网格的反应堆控制棒落棒行为分流域耦合仿真方法;莫锦涛;方浩宇;陈训刚;颜达鹏;李长香;邓朝俊;牛昊轩;;中国核电;20200615(第03期);第328-332页 * |
| 分体式控制棒组件换料工艺路线设计;王浩仲;吴水金;杨孔雳;谷继品;苏喜平;夏凡;刘川川;;科技创新导报(第19期);第55-58页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN113871041A (en) | 2021-12-31 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103003888B (en) | control rod drive rod unlocking tool | |
| CN113871041B (en) | Method for installing, removing and replacing control rod assembly | |
| CN112837832B (en) | Rotary type material-changing special structure for changing outer sleeve of control rod assembly | |
| JPH0578797B2 (en) | ||
| CN112863715B (en) | Rotary type material changing special structure for replacing control rod assembly moving body | |
| JPS5999298A (en) | Device of gripping many fuel rods | |
| CN110600145B (en) | Locking, unlocking and grabbing lifting device for lead-based reactor fuel assembly | |
| US3044947A (en) | Apparatus for loading and unloading a machine | |
| US4716018A (en) | End plug with truncated tapered leading end configuration | |
| JPH0458911B2 (en) | ||
| CN112863716B (en) | A special structure of formula of pushing down reloading for changing control rod assembly moving body | |
| EP0221641B1 (en) | Reconstitutable nuclear fuel assembly | |
| CN113871043B (en) | Method for replacing outer sleeve of control rod assembly in reactor core | |
| JPS61162788A (en) | Inserter of locking tube for fuel aggregate | |
| US20090257545A1 (en) | Reinforcement for a nuclear fuel assembly | |
| CN101850545B (en) | Manipulator for disassembling and assembling lifting bucket of fast reactor loading and unloading material hoister | |
| KR100867031B1 (en) | Refueling Machine Grapple | |
| CN113871042B (en) | Material changing device for control rod assembly moving body | |
| CN110718311B (en) | A first mechanism is grabbed in reloading for lead-based reactor fuel assembly | |
| CN113963823A (en) | Reactor refueling system and refueling method | |
| RU2562055C2 (en) | Sealed used nuclear fuel package for reactor lwgr-1000 | |
| US3597317A (en) | Nuclear reactor fuelling machine | |
| US4183785A (en) | Method for positioning moderator structure for the core of a molten-salt reactor | |
| CN106663480A (en) | Method of extracting plug and removable unit when refueling nuclear reactor | |
| CN206545488U (en) | The vertical land hoisting tool of production tree |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |