CN113871041A - Control rod assembly mounting method, control rod assembly removing method and control rod assembly replacing method - Google Patents
Control rod assembly mounting method, control rod assembly removing method and control rod assembly replacing method Download PDFInfo
- Publication number
- CN113871041A CN113871041A CN202111129136.9A CN202111129136A CN113871041A CN 113871041 A CN113871041 A CN 113871041A CN 202111129136 A CN202111129136 A CN 202111129136A CN 113871041 A CN113871041 A CN 113871041A
- Authority
- CN
- China
- Prior art keywords
- refueling
- sleeve
- special
- tool
- reactor
- 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.)
- Granted
Links
- 238000000034 method Methods 0.000 title claims abstract description 107
- 239000000446 fuel Substances 0.000 claims description 17
- 238000000429 assembly Methods 0.000 claims description 10
- 230000000712 assembly Effects 0.000 claims description 10
- 239000011800 void material Substances 0.000 claims description 9
- 238000009434 installation Methods 0.000 abstract description 16
- 230000008569 process Effects 0.000 description 29
- 239000000463 material Substances 0.000 description 17
- 239000003758 nuclear fuel Substances 0.000 description 11
- 230000008859 change Effects 0.000 description 6
- 238000010586 diagram Methods 0.000 description 6
- 239000002915 spent fuel radioactive waste Substances 0.000 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 description 2
- 230000009471 action Effects 0.000 description 2
- 238000010276 construction Methods 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
- 238000007599 discharging Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000011900 installation process Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Images
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 method of installing, removing and replacing a control rod assembly. The control rod assembly includes a moving body and an outer sleeve. Wherein the method of installing a control rod assembly within a reactor core comprises: the reactor exterior locks the refueling specific tool with the outer sleeve; placing the locked refueling specific tool and the outer sleeve at a core vacancy within the reactor; unlocking the refueling specific tool from the outer sleeve; and removing the refueling specific tool from within the outer sleeve. The invention provides an installation method suitable for a split type 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 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, 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 replacement, installation or removal of the control rod assembly in the reactor core.
Disclosure of Invention
A first aspect of the invention provides a method of mounting a control rod assembly within a reactor core, the control rod assembly comprising a mobile body and an outer sleeve, the method comprising:
providing a refueling special tool lockable or unlockable with the outer sleeve within the outer sleeve;
locking the refueling specific tool with the outer sleeve outside the reactor;
placing the locked refueling specific tool and the outer sleeve at a core operating site within the reactor core;
unlocking the refueling specific tool from the outer sleeve; and
removing the refueling specific tool from within the outer sleeve.
The invention provides a method for taking out a control rod assembly from 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 reloading is arranged in the first reserved vacancy; the method comprises the following steps:
providing a refueling special sleeve, wherein the moving body can be locked or unlocked with the refueling special sleeve in the refueling special sleeve;
providing a refueling special tool capable of being locked or unlocked with the outer sleeve and the refueling special sleeve within the outer sleeve and the refueling special sleeve, respectively;
locking the refueling specific tool with the refueling specific sleeve outside the reactor;
placing the locked refueling specific tool and the refueling specific sleeve at the second reserved void within the reactor core;
transferring the moving body into the temporary storage sleeve;
unlocking the special refueling tool and the special refueling sleeve;
transferring the refueling specific tool into the outer sleeve to be locked with the outer sleeve; and
removing the locked refueling specific tool and the outer sleeve out of the reactor core.
A third aspect of the invention provides a method of replacing a control rod assembly, the control rod assembly including a mobile body and an outer sleeve, the method comprising:
according to the taking-out method, the special refueling tool and the spent outer sleeve are moved out of the reactor, and the spent moving body and the special refueling sleeve are moved out of the reactor;
according to the installation method described above, the new outer sleeve is moved into the core operating position of the reactor core, and the new moving body 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 which refers to the accompanying drawings, and may assist in a comprehensive understanding of the invention.
FIG. 1 is a schematic diagram of a special tool for refueling used in accordance with an embodiment of the present application;
FIG. 2 is a cross-sectional view of the fit between the grab sleeve, the small grid header, the locked refueling specific tool, and the outer sleeve;
FIG. 3 is a cross-sectional view taken along A-A of FIG. 2;
FIG. 4 is a schematic structural diagram of a refueling cartridge used in accordance with an embodiment of the present application;
FIG. 5 is a cross-sectional view taken along line B-B of FIG. 4;
FIG. 6 is a view of the cooperation between the grab sleeve, the small grid header, the locked refueling cartridge and the mobile body;
FIG. 7 is a cross-sectional view taken along the line C-C of FIG. 6;
FIG. 8 is an enlarged partial view of area D of FIG. 6;
FIG. 9 is a flow chart of a method of installing a control rod assembly within a reactor core according to one embodiment of the invention;
FIG. 10 is a flow chart of a method of installing a control rod assembly within a reactor core according to another embodiment of the invention;
FIG. 11 illustrates core changes during installation of a control rod assembly in a reactor core;
FIG. 12 is a flow diagram of a method of removing a control rod assembly from a reactor core according to one embodiment of the invention;
FIG. 13 illustrates the core change during removal of the control rod assembly 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 is noted that the drawings are not necessarily to scale and are merely illustrative in nature and not intended to obscure the reader.
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. In the related art, the moving body and the outer sleeve are usually replaced individually or the outer sleeve is replaced individually.
In the related art, the moving body and the outer sleeve have respective refueling processes. In the refueling process of the moving body or the outer sleeve, a new-to-old replacement mode is adopted, namely, a refueling special tool (or a refueling special sleeve) is used for carrying a new outer sleeve (or a new moving body) to enter the reactor core, and then a spent outer sleeve (or a spent moving body) is carried out of the reactor. Specifically, the refueling special tool can be locked or unlocked with the outer sleeve in the outer sleeve; in the reactor core, the operating head of the special refueling tool can be grabbed by the refueling machine of the reactor refueling system to drive the special refueling tool to move, 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 reactor core refueling system, so that the new outer sleeve can be unlocked from the special refueling tool after the new outer sleeve is placed in the core working position, the special refueling tool is locked with the outer spent sleeve, and then the special refueling tool is used for carrying the outer spent sleeve to move out of the core.
Accordingly, the moving body can be locked or unlocked with the refueling cartridge within the refueling cartridge. In the reactor, the moving body is driven to move by an operating head of the moving body grabbed by a refueling machine of the refueling system in the reactor, so that the special refueling sleeve is driven to move. In addition, in the reactor, the moving body and the special refueling sleeve can be locked or unlocked through the refueling machine of the reactor refueling system alone or in cooperation with the cock, so that the new moving body and the special refueling sleeve can be unlocked, the new moving body is placed in the outer core sleeve and then locked with the spent moving body and the special refueling sleeve, and the spent moving body is used for carrying the special refueling sleeve to move out of the reactor core.
Due to the fact that equipment in the in-pile and out-pile refueling systems is as follows: the loading and unloading hoister, 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 tool for changing the materials is short of the size of an interface with the equipment, so that the reactor core cannot be transported out by the single special tool for changing the materials, the special tool for changing the materials 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 removal of the refueling specific tool from the reactor must be considered when designing the replacement outer sleeve.
In the related art, for such a refueling process, at the time of initial installation of a reactor core, a control rod assembly model is manually placed at a reactor core working position, the control rod assembly model includes a moving body model and an outer sleeve model, wherein the moving body model has the same shape as the moving body, but no neutron absorbing material is provided inside; the outer sleeve model is the same shape as the outer sleeve. After the reactor core is installed, through the cooperation of the refueling machine of the refueling system in the reactor or the cock, the outer sleeve model is replaced by a new outer sleeve by using a special refueling tool, and the moving body model is replaced by a new moving body by using the special refueling sleeve, so that the control rod assembly is installed.
While the moving body and the outer sleeve need to be replaced at the same time every few years (e.g., 3 years) when the reactor is operated, the efficiency of replacing the moving body or the outer sleeve separately in the related art is too low.
In addition, during reactor decommissioning, all control rod assemblies need to be removed from the reactor. In the related art, all control rod assemblies can only be replaced with control rod assembly models in a manner that "new" replaces "old.
It can be seen that in the related art, whether the control rod assembly is installed for the first time in the reactor core, or the moving body and the outer sleeve are replaced at the same time, or the reactor is out of service, the moving body or the outer sleeve needs to be installed (or removed) separately, and only the new mode of replacing the old mode with the new mode can be adopted, and obviously, the replacement efficiency of the replacement process is too low.
The invention thus provides a new method of changing a split control rod assembly in which, in particular, a change tool and a change sleeve are arranged such that the change tool can be locked or unlocked within the change sleeve. For example, the structure of the special refueling sleeve in the related art can be improved, so that the special refueling sleeve has a locking structure similar to that of the outer sleeve, and locking and unlocking with a special refueling tool are realized. 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 separately carried out, when the spent control rod assembly is moved out, the special sleeve for refueling is carried by the special refueling tool to enter the reactor, and the special sleeve for refueling and the new moving body are respectively carried by the spent moving body and the spent outer sleeve to exit the reactor; when a new control rod assembly is installed, the refueling special tool and the refueling special sleeve respectively carry the new outer sleeve and the new moving body to enter the reactor core, and then the refueling special tool carries the refueling special sleeve to be moved out of the reactor. Therefore, the invention can simultaneously move out (or install) the moving body and the outer sleeve of the control rod assembly, thereby improving the replacement efficiency of the split control rod assembly.
In the embodiment of the invention, the special tool for changing the material can be inserted into the outer sleeve, and the special tool for changing the material and the outer sleeve can be mutually locked (or locked) and unlocked; the moving body can be inserted into the refueling special sleeve, and the moving body and the refueling special sleeve can be mutually locked (or locked) and unlocked. When the special tool for refueling is locked with the outer sleeve, the external structure of the special tool is similar to that of the fuel assembly; when the special sleeve for refueling is locked with the moving body, the external structure of the special sleeve is similar to that of the fuel assembly, and all related equipment in the existing refueling system can be compatible. Meanwhile, the special refueling tool can be inserted into the special refueling sleeve and can be locked (or locked) and unlocked mutually, and when the special refueling tool is locked, the appearance structure of the special refueling tool is similar to that of a fuel assembly, and the special refueling tool can also be compatible with related equipment in the existing refueling system.
Fig. 1 is a schematic structural diagram of a special tool for refueling adopted according to an embodiment of the application. Referring to FIG. 1, a control rod assembly outer sleeve refueling specialty tool 100 may include: an operating head 110, a sleeve assembly 120 fixedly connected with the operating head 110, and a bottom structure 130.
The operating head 110 may be shaped similar to the operating head of a fuel rod in order to adapt the entire refueling system, e.g. a new component loader, a transfer machine, a grab sleeve for a refueling machine, a pool handler, etc. may grab the operating head 110 of the refueling specific tool 100.
The operating head 110 may include a head 111, a shoulder 113, and a connecting portion 112 connecting the head 111 and the shoulder 113. The head 111 and the shoulder 113 of the operating head 110 each include, in order, a circular truncated portion with a gradually expanding diameter, a cylindrical portion with a uniform diameter, and a circular truncated portion with a gradually contracting diameter. 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 limiting protrusions 1131 along the circumferential direction for matching with a plurality of vertical grooves on the gripper sleeve of the refueling system in the reactor. When the grip sleeve is used to grip the operating head 110, the grip sleeve acts on the shoulder 113 of the operating head 110, a vertical groove with a lower opening is formed in the grip sleeve, and the limiting protrusion 1131 of the operating head 110 is located in the vertical groove, so that the grip sleeve can drive the tool 100 special for material changing to rotate.
FIG. 2 is a cross-sectional view of the fit between the grab sleeve, the small grid header, the locked refueling specific tool, and the outer sleeve. Referring to fig. 2, the outer sleeve 200 is inserted into the insert (i.e., core operating site) of the small grid header 300 through the pins 25 thereof. Sleeve assembly 120 and base structure 130 of the refueling specific tool 100 are located inside outer sleeve 200.
A spring 24 and a locking sleeve 23 are provided in the prongs 25 of the outer sleeve 200. The locking sleeve 23 is slidable axially up and down and the 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 cross-section of the recess and bottom structure 130 of locking sleeve 23 is hexagonal so that locking sleeve 23 can rotate about the axis with the glove box 400 (at which time outer sleeve 200 remains stationary relative to small grid box 300 and locking sleeve 23 rotates relative to small grid box 300) in conjunction with the refueling specific tool 100.
The bottom structure 130 is provided with a plurality of bosses 131 in the circumferential direction. A plurality of bosses 21 are arranged in the outer sleeve 200, and a slot 22 is formed between two adjacent bosses 21. When the tool 100 is rotated about the axis by the grip sleeve 400, the boss 131 of the substructure 130 may be located below the boss 21 or below the slot 22.
After the tool 100 is rotated by a predetermined angle around the axis by the grip sleeve 400, if the boss 131 of the bottom structure 130 is located below the boss 21, the grip sleeve 400 is moved upward, and the tool 100 is moved upward by 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 the tool 100 is rotated about the axis by the grip sleeve 400 by a predetermined angle, the tool 100 is unlocked from the outer sleeve 200 inside the outer sleeve 200 if the bosses 131 of the bottom structure 130 are located below the slots 22 (as shown in fig. 3). At this point, the grip sleeve 400 may drive the refueling specific tool 100 to move upward away from the outer sleeve 200.
The circumferential wall of the locking sleeve 23 is provided with a pin, and when the locking sleeve 23 rotates around the axis under the action of the grab sleeve 400 together with the special tool 100 for reloading, the pin can be locked or unlocked with the limit groove arranged on the small grid plate header 300.
Fig. 4 is a schematic structural diagram of a refueling cartridge used according to an embodiment of the present application. Fig. 5 is a sectional view taken along the direction B-B in fig. 4. Referring to fig. 4 and 5, the refueling cartridge 500 includes a main tube 52, a pin 53, a moving body locking structure 51, and a refueling tool locking structure.
The main tube 52 is formed with a receiving chamber therein for receiving the moving body 600 of the control rod assembly. The pins 53 are fixedly connected to the lower end of the main pipe 52, and support the main pipe 52, and the pins 53 can be inserted into the small grid plate header 300 of the core.
FIG. 6 is a view of the cooperation between the grab sleeve, the small grid header, the locked refueling cartridge and the 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 area D in fig. 6. Referring to fig. 4 to 8, the moving body locking structure 51 is used to cooperate with an annular groove 601 on an operating head 610 of the moving body 600 to lock or unlock the moving body 600 with the refueling cartridge 500.
In the illustrated embodiment, the car lock structure 51 includes a first tube 511, a movable sleeve 512, and a spring 513.
The lower end of the first pipe 511 is fixedly connected to the main pipe 52, and a plurality of balls 5111 capable of moving in the radial direction are disposed on the pipe wall of the first pipe 511 along the circumferential direction. The movable sleeve 512 is movably sleeved on the first tube 511. The upper end of the movable sleeve 512 extends upward to form a protrusion 5121. Through the cooperation of the protrusion 5121 and the vertical groove of the hand grip sleeve 400, the circumferential positioning of the movable sleeve 512 and the hand grip sleeve 400 is realized, so that when the hand 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 when the movable sleeve 512 rotates around the axis relative to the first tube 511, the balls 5111 can move radially inward to the locking position or radially outward to the unlocking position. In the locking position, the balls 5111 are engaged with the annular groove 601 of the moving body 600, thereby achieving locking of the refueling cartridge 500 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 refueling cartridge 500 from the moving body 600.
Specifically, in the process that the grip sleeve 400 drives the movable sleeve 512 to rotate, if the balls 5111 are staggered from the receiving groove of the movable sleeve 512, the balls 5111 move radially inward 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 unlocked position.
The spring 513 is disposed on the first tube 511 and is used for providing an axial upward abutting force to the movable sleeve 512 so as to keep the movable sleeve 512 at an upper position of the first tube 511. The spring 513 may be a compression spring, for example.
The refueling tool locking structure includes a plurality of bosses extending radially inward from the inner wall of the main tube body 52, and a slot is formed between two adjacent bosses. The locking structure of the refueling tool is similar to that of the outer sleeve, and is not described in detail herein.
Since the refueling tool locking structure is similar to that of the outer sleeve, the refueling tool can be locked or unlocked with the special sleeve through the refueling tool locking structure.
In the method of embodiments of the invention, two voids may be reserved at the reactor core storage well (i.e., the small grid header): the control rod assembly comprises a first reserved vacancy and a second reserved vacancy, wherein the second reserved vacancy is completely vacated, the first reserved vacancy is preset with an outer sleeve as a temporary storage sleeve, and the control rod assembly is replaced in the reactor core through the arrangement.
Since the moving body (or the outer sleeve) is separated from the putting-in process of the new moving body (the new outer sleeve), and the moving body and the outer sleeve of the control rod assembly can be moved out or installed at the same time. Thus, the replacement method of the present invention may be further extended to a method of installing a control rod assembly in a reactor core and a method of removing a control rod assembly from a reactor core. Therefore, when the control rod assembly is installed at the reactor core for the first time, the control rod assembly model does not need to be manually placed at the reactor core working position, and a new control rod assembly can be installed into the reactor core working position after the reactor core is installed; and, the spent control rod assemblies can also be completely swapped out of the reactor during reactor decommissioning without the need for replacement with a control rod assembly model.
Fig. 9 is a flowchart of a method of installing a control rod assembly in a reactor core according to an embodiment of the invention, and referring to fig. 9, a method of installing a control rod assembly in a reactor core (hereinafter referred to as an installation method) according to an embodiment of the invention includes steps S100 to S108.
Step S100, providing a special refueling tool, wherein the special refueling tool can be locked or unlocked with the outer sleeve in the outer sleeve;
step S102, locking the special tool for reloading and the outer sleeve;
step S104, placing the locked refueling specific tool and the outer sleeve at a core operating position in the reactor core;
step S106, unlocking the special tool for reloading and the outer sleeve; and
and step S108, removing the special refueling tool from the outer sleeve.
In step S100, a special tool for refueling is provided as shown in fig. 1, which can be locked or unlocked with the outer sleeve inside the outer sleeve.
In step S102, the refueling specific tool may be locked with the outer sleeve within a new fuel depot. The installation method further comprises the following steps: transporting the locked refueling specific tool and the outer sleeve into a reactor lobby; and then the locked refueling special tool and the outer sleeve are transported to the reactor core of the reactor through the in-reactor and out-of-reactor refueling system.
In step S104, an operation head of a refueling tool is grasped by a refueling machine of the in-reactor refueling system within the reactor, and the locked refueling tool and the outer sleeve are placed at a core operating site within the reactor core. As will be readily understood by those skilled in the art, in the present application, when a control rod assembly is installed in a reactor core, there are a plurality of core worksites within the core for installing the control rod assembly. The installation process may be when the control rod assembly is first installed on the reactor core or when the control rod assembly is replaced. When the control rod assembly is replaced, the spent mobile body and the spent outer sleeve of at least one control rod assembly are moved out of the core so as to leave at least one core operating position for installing the new outer sleeve and the new mobile body at the core.
In step S106, after the locked refueling specific tool and the outer sleeve are placed at the core operating site in the reactor core, the refueling specific tool and the outer sleeve may be unlocked by cooperation of a refueling machine and a cock of the in-reactor refueling system, and the outer sleeve is locked with the small grid plate header while the refueling specific tool is unlocked with the outer sleeve.
In step S108, the unlocked refueling specific tool is removed from the outer sleeve by the refueling machine of the in-pile refueling system.
The outer sleeve of the control rod assembly is installed at a core operating site within the reactor core through steps S100 to S108.
In some embodiments, the reactor core is reserved with a first reserved vacant space, and a temporary storage sleeve for temporarily storing the refueling special tool is arranged in the first reserved vacant space. It is easy to understand that the reactor core vacancy is a reactor core vacancy on the small grid plate header and is specially used for placing the temporary storage sleeve. In some embodiments, the position of the first reserved space remains unchanged, i.e. one core space fixed on the small grid header is used for placing the temporary storage sleeve.
In such embodiments, after step S108, the installation method may further include step S110 of transferring the refueling specific tool into the staging sleeve.
In some embodiments, the reactor core is reserved with a second reserved void, which is also a 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 step S112 to step S120 after step S108 or after step S110 to place the moving body within the outer sleeve.
Step S112, providing a special refueling sleeve, wherein the moving body can be locked or unlocked with the special refueling sleeve in the special refueling sleeve;
step S114, locking the moving body and the refueling special sleeve;
step S116, the locked moving body and the special refueling sleeve are placed at the second reserved vacant position;
step S118, unlocking the moving body and the refueling special sleeve;
step S120 of transferring the mobile body into the outer sleeve.
Through the steps S100 to S120, the outer sleeve is placed at the core operating position, and the moving body is placed in the outer sleeve, so that the installation of the group of control rod assemblies is completed.
In step S112, a refueling cartridge is provided as shown in fig. 4, and the movable body can be locked or unlocked with the refueling cartridge in the refueling cartridge.
In step S114, the movable body may be locked with the refueling cartridge in a new fuel storage. The installation method further comprises the following steps: the locked moving body and the refueling special sleeve are conveyed into a reactor hall; and then the locked moving body and the refueling special sleeve are transported to the reactor core of the reactor through the in-reactor and out-reactor refueling system.
In step S116, an operating head of a moving body is grasped by a refueling machine of the in-reactor refueling system within the reactor, and the locked moving body and the refueling specific sleeve are placed at a second reserved vacant site within the reactor core.
In step S118, after the locked moving body and the refueling special sleeve are placed in the second reserved vacant space, the moving body and the refueling special sleeve can be unlocked by cooperation of a refueling machine and a cock of the in-stack refueling system.
In step S120, the mobile body after the unlocking is transferred to the outer sleeve by the stocker of the in-pile refueling system.
In some embodiments, the refueling specific tool is configured to be lockable or unlockable with the refueling specific sleeve within the refueling 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 specific tool and the refueling specific sleeve out of the reactor.
Step S122, transferring the special tool for material changing into the special sleeve for material changing, and locking the special tool for material changing with the special sleeve for material changing;
and step S124, moving the locked special refueling tool and the special refueling sleeve out of the reactor.
In step S122, after transferring the refueling specific tool into the refueling specific sleeve, the refueling specific tool may be locked with the refueling specific sleeve using cooperation of a refueling machine and a cock of an in-stack refueling system.
In step S124, the locked refueling specific tool and refueling specific sleeve may be transported to the outside of the reactor by using a charging and discharging hoist.
As will be understood by those skilled in the art, the transfer of the refueling specific tool and the mobile body, as well as the unlocking of the refueling specific tool from the outer sleeve, the unlocking of the mobile body from the refueling specific sleeve, and the locking of the refueling specific tool from the refueling specific sleeve, may be accomplished within the reactor by cooperation of a refueling machine and a cock of the refueling system within the reactor.
In some embodiments, the construction of the escrow sleeve may be the same as the construction of the outer sleeve.
In some embodiments, prior to placing the locked refueling specific tool and the outer sleeve at a core operating site within the reactor core, the installation method further comprises: locking the special tool for refueling and the temporary storage sleeve outside the reactor; placing the locked refueling specific tool and the staging sleeve at a first reserved void within the reactor core; unlocking the special tool for reloading and the temporary storage sleeve; and moving the special tool for replacing materials out of the temporary storage sleeve. That is, the temporary storage sleeve may be placed at the first reserved empty location in advance before the control rod assembly is installed in the core.
In some embodiments, the refueling specific tool may be locked with the staging sleeve within a new fuel depot; the installation method further comprises the following steps: the locked special refueling tool and the temporary storage sleeve are conveyed into a reactor hall; and transporting the locked refueling specific tool and the temporary storage sleeve into the reactor core.
Of course, in some embodiments, the temporary sleeves may also be manually placed when the control rod assemblies are first installed on the reactor core (i.e., prior to filling the reactor with sodium).
FIG. 11 illustrates core changes during installation of a control rod assembly in a reactor core.
The initial state of the reactor core is shown in fig. 11 a. The reactor core is provided with a reactor core working position 30, 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 installing the control rod assembly includes:
(1) placing the locked refueling specific tool 6 and the new outer sleeve 7 at the core operating position 30 (see fig. 11b) by the cooperation of the cock and the refueling machine;
(2) by means of the cooperation of the cock with the refueling machine, the special refueling tool 6 is unlocked from the new outer sleeve 7 and the special refueling tool 6 is transferred into the temporary storage sleeve 4 located in the first reserved empty space 31, at which time the new outer sleeve 7 is empty (see fig. 11 c);
(3) the locked special refueling sleeve 5 and the new moving body 8 are placed into the second reserved vacant position 32 through the matching operation of the cock and the refueling machine (see fig. 11 d);
(4) by the operation of the refueling machine, the new moving body 8 is unlocked from the refueling special sleeve 5, the new moving body 8 is placed into the new outer sleeve 7, and the new control rod assembly completes the charging operation (see fig. 11 e);
(5) by means of the cooperation of the cock and the refueling machine, the refueling specific tool 6 located in the temporary storage sleeve 4 is placed into the refueling specific sleeve 5 located in the second reserved empty space 32 (see fig. 11f) and both are locked and transported out of the reactor (see fig. 11g, i.e. the state where a new set of control rod assemblies is installed on the reactor core).
Embodiments of the present invention also provide a method of removing a control rod assembly from a reactor core. The reactor core is reserved with a first reserved vacancy and a second reserved vacancy, wherein a temporary storage sleeve used for temporarily storing the special tool for refueling is arranged in the first reserved vacancy.
FIG. 12 is a flow diagram of a method of removing a control rod assembly from a reactor core according to one embodiment of the invention. Referring to fig. 12, the method of removing the control rod assembly from the reactor core (hereinafter referred to as a removal method) includes steps S200 to S212.
Step S200, providing a special sleeve for reloading, wherein the moving body can be locked or unlocked with the special sleeve for reloading in the special sleeve for reloading; providing a refueling special tool capable of being locked or unlocked with the outer sleeve and the refueling special sleeve within the outer sleeve and the refueling special sleeve, respectively;
step S202, locking the special tool for changing materials and the special sleeve for changing materials;
step S204, placing the locked refueling special tool and the refueling special sleeve at the second reserved vacant position in the reactor core;
step S206, transferring the moving body into the temporary storage sleeve;
step S208, unlocking the special refueling tool and the special refueling sleeve;
step S210, transferring the special tool for reloading into the outer sleeve and locking the special tool with the outer sleeve;
and S212, moving the locked refueling special tool and the outer sleeve out of the reactor.
Through steps S200 to S212, the outer sleeve is removed from the core.
In step S200, a special tool for refueling is provided as shown in fig. 1, which can be locked or unlocked with the outer sleeve inside the outer sleeve. As shown in fig. 4, the refueling cartridge is provided such that the movable body can be locked or unlocked with the refueling cartridge in the refueling cartridge.
In step S202, locking the refueling specific tool with the refueling specific sleeve in a new fuel storage; the method of removing further comprises transporting the locked refueling specific tool and the refueling specific sleeve into a reactor lobby; and transporting the locked refueling specific tool and the refueling specific sleeve into the reactor core.
In some embodiments, after unlocking the refueling specific tool from the refueling specific sleeve, the method further comprises: transferring the moving body into the refueling special sleeve to be locked with the refueling special sleeve; and moving the locked moving body and the refueling special sleeve out of the reactor. Thereby, the moving body is moved out of the core.
In the reactor, the transfer of the refueling special tool and the moving body, the unlocking of the refueling special tool and the refueling special sleeve, the locking of the refueling special tool and the outer sleeve and the locking of the moving body and the refueling special sleeve are realized through the cooperation of a refueling machine and a cock of the refueling system in the reactor.
In some embodiments, the method of removing further comprises: locking the refueling specific tool with the temporary storage sleeve outside the reactor, and placing the locked refueling specific tool and the temporary storage sleeve at the first reserved vacancy in the reactor core; unlocking the special tool for reloading and the temporary storage sleeve; and moving the special tool for replacing materials out of the temporary storage sleeve. That is, the temporary storage sleeve can be placed at the first reserved empty position in advance.
Of course, in some embodiments, the temporary sleeves may also be manually placed when the control rod assemblies are first installed on the reactor core (i.e., prior to filling the reactor with sodium).
FIG. 13 illustrates the change in core vacancy during removal of the control rod assembly from the reactor core.
The initial state of the reactor core is shown in fig. 13 a. 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 special tool 6 and the refueling special sleeve 5 to a second reserved vacant position 32 in the reactor core by matching a refueling machine of the in-reactor refueling system with a cock (see fig. 13 b);
(2) the spent moving body 2 of the spent control rod assembly needing to be replaced in the reactor core is transferred into the temporary storage sleeve 4 at the first reserved vacant position 31 through the matching of the refueling machine and the cock, and the spent outer sleeve 1 of the spent control rod assembly needing to be replaced is emptied (see fig. 13 c);
(3) unlocking the refueling special tool 6 locked at the second reserved vacant position 32 and the refueling special sleeve 5 through a refueling machine operation, then transferring the refueling special tool 6 into the spent outer sleeve 1 vacated in the core, and locking the refueling special tool 6 and the spent outer sleeve 1 (see fig. 13 d);
(4) the spent moving body is drawn out from the temporary storage sleeve 4 at the first reserved vacant position 31 and transferred into the special refueling sleeve 5 at the second reserved vacant position 32 through the matching of the refueling machine and the cock, and the spent moving body 2 and the special refueling sleeve 5 are locked (see fig. 13 e);
(5) and (4) conveying the locked special refueling sleeve 5, the spent moving body 2, the special refueling tool 6 and the spent outer sleeve 1 out of the reactor (see fig. 13 f).
The embodiment of the invention also provides a method for replacing the control rod assembly aiming at the condition that the moving body and the outer sleeve simultaneously reach the refueling period. The reactor core is reserved with a first reserved vacancy and a second reserved vacancy, wherein a temporary storage sleeve used for temporarily storing the special tool for refueling 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 special sleeve and a special tool for material changing;
step S302, removing the refueling special tool and the outer sleeve from the reactor core vacancy;
step S304, moving the spent moving body and the refueling special sleeve out of the reactor from the second reserved vacant site;
step S306, moving the new outer sleeve into a core working position of the reactor core;
in step S308, the new mobile body is moved into the new outer sleeve.
In step S302 and step S304, the refueling tool and the spent outer sleeve are removed from the reactor by the above-described removal method, and the spent moving body and the refueling sleeve are removed from the reactor.
In steps S306 and S308, the new outer sleeve is moved into the core operating site of the reactor core by the installation method described above, and the new moving body is moved into the new outer sleeve.
The refueling process flow for the split type control rod replacement assembly provided by the invention is described in detail 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 transporting the locked special refueling tool and the locked special refueling sleeve to a reactor hall through a new assembly process transportation route in the existing assembly refueling process route;
2. after the two are transported to a reactor hall, the locked special refueling tool and the locked special refueling sleeve are transported to the reactor core of the reactor through the outside-reactor and inside-reactor refueling process routes in the existing component refueling process routes;
3. within the reactor core:
the initial state of the reactor core is shown in fig. 13 a. 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 special tool 6 and the refueling special sleeve 5 to a second reserved vacant position 32 in the reactor core by matching a refueling machine of the in-reactor refueling system with a cock (see fig. 13 b);
(2) the spent moving body 2 of the spent control rod assembly needing to be replaced in the reactor core is transferred into the temporary storage sleeve 4 at the first reserved vacant position 31 through the matching of the refueling machine and the cock, and the spent outer sleeve 1 of the spent control rod assembly needing to be replaced is emptied (see fig. 13 c);
(3) unlocking the refueling special tool 6 locked at the second reserved vacant position 32 and the refueling special sleeve 5 through a refueling machine operation, then transferring the refueling special tool 6 into the spent outer sleeve 1 vacated in the core, and locking the refueling special tool 6 and the spent outer sleeve 1 (see fig. 13 d);
(4) the spent moving body 2 is drawn out from the temporary storage sleeve 4 at the first reserved vacant position 31 and transferred into the special refueling sleeve 5 at the second reserved vacant position 32 through the matching of the refueling machine and the cock, and the spent moving body 2 and the special refueling sleeve 5 are locked (see fig. 13 e);
(5) and (4) conveying the locked special refueling sleeve 5, the spent moving body 2, the special refueling tool 6 and the spent outer sleeve 1 out of the reactor (see fig. 13 f).
4. Transporting the spent moving body 2 transported out of the reactor, the special sleeve 5 for refueling, the outer sleeve 1 for spent fuel and the special tool 6 for refueling to a spent fuel water pool for storage through a spent component process transportation route in the existing component refueling process route;
5. locking the refueling special tool with the new outer sleeve and the new moving body with the refueling special sleeve in the new fuel warehouse, and then transporting the refueling special tool into a reactor hall through a new assembly process transportation route in the existing assembly refueling process route;
6. after the two are transported to a reactor hall, the locked special refueling tool and the new outer sleeve, the new moving body and the special refueling sleeve are transported to the reactor core of the reactor through the outside-reactor and inside-reactor refueling process routes in the existing component refueling process routes;
7. within the reactor core:
(1) placing the locked refueling specific tool 6 and the new outer sleeve 7 at the core operating site 30 (see fig. 11b) by means of a cock cooperating with the refueling machine;
(2) by means of the operation of the cock and the refueling machine, the special refueling tool 6 is unlocked from the new outer sleeve 7 and the special refueling tool 6 is transferred into the temporary storage sleeve 4 located in the first reserved vacant position 31, the new outer sleeve 7 is vacant (see fig. 11 c);
(3) the locked special refueling sleeve 5 and the new moving body 8 are placed into the second reserved vacant position 32 through the matching operation of the cock and the refueling machine (see fig. 11 d);
(4) by the operation of the refueling machine, the new moving body 8 is unlocked from the refueling special sleeve 5, the new moving body 8 is placed into the new outer sleeve 7, and the new control rod assembly completes the charging operation (see fig. 11 e);
(5) by means of the operation of the cock and the refueling machine, the refueling specific tool 6 located in the temporary storage sleeve 4 is placed into the refueling specific sleeve 5 located in the second reserved empty space 32 (see fig. 11f) and both are locked out of the reactor (see fig. 11g, i.e. the state of the reactor core where a new set of control rod assemblies is installed).
8. And (3) transporting the special refueling sleeve of the refueling special tool transported out of the reactor core to a spent fuel pool for storage through a spent component process transportation route in the existing component refueling process route.
Therefore, the embodiment of the invention has 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 influence the refueling operation of the fuel assembly;
(3) the replacement efficiency of the split control rod assembly can be improved through the material replacement process;
(4) the spent control rod assembly can be completely replaced out of the reactor when the reactor is out of service through the material replacement process flow;
(5) through the refueling process flow, when the reactor core is completely replaced by the spent control rod assembly, the new control rod assembly can be loaded into the reactor core.
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 (16)
1. A method of installing a control rod assembly within a reactor core, the control rod assembly including a traveling body and an outer sleeve, the method comprising:
providing a refueling special tool lockable or unlockable with the outer sleeve within the outer sleeve;
locking the refueling specific tool with the outer sleeve outside the reactor;
placing the locked refueling specific tool and the outer sleeve at a core worksite within the reactor;
unlocking the refueling specific tool from the outer sleeve; and
removing the refueling specific tool from within the outer sleeve.
2. The method of claim 1, wherein a first reserved vacancy is reserved in the reactor core, and a temporary storage sleeve for temporarily storing the tool special for refueling is arranged in the first reserved vacancy;
the method further comprises, after removing the refueling specialized tool from within the outer sleeve:
transferring the special tool for reloading into the temporary storage sleeve.
3. The method of claim 1 or 2, wherein the reactor core is reserved with a second reserved void,
the method further comprises, after removing the refueling specialized tool from within the outer sleeve:
providing a refueling special sleeve, wherein the moving body can be locked or unlocked with the refueling special sleeve in the refueling special sleeve;
locking the moving body with the refueling cartridge outside the reactor;
placing the locked moving body and the refueling special sleeve at a second reserved vacant position of the reactor core;
unlocking the moving body and the refueling special sleeve; and
transferring the mobile body into the outer sleeve.
4. The method of claim 3, wherein the refueling specific tool is lockable or unlockable with the refueling specific sleeve within the refueling specific sleeve;
the method further comprises, after unlocking the mobile body from the refueling cartridge, the steps of:
transferring the special tool for refueling into the special sleeve for refueling, and locking the special tool for refueling with the special sleeve for refueling; and
moving the locked refueling specific tool and refueling specific sleeve out of the reactor.
5. The method of claim 4,
in the reactor, the transfer of the refueling special tool and the moving body, the unlocking of the refueling special tool and the outer sleeve, the unlocking of the moving body and the refueling special sleeve, and the locking of the refueling special tool and the refueling special sleeve are realized through the cooperation of a refueling machine and a cock of the refueling system in the reactor.
6. The method of claim 2,
the structure of the temporary storage sleeve is the same as that of the outer sleeve.
7. The method of claim 1, wherein said locking the refueling specific tool with the outer sleeve outside the reactor comprises:
locking the refueling specific tool with the outer sleeve within a new fuel depot;
the method further comprises the following steps:
transporting the locked refueling specific tool and the outer sleeve into a reactor lobby; and
the locked refueling specific tool and the outer sleeve are transported into the reactor core.
8. The method of claim 3, wherein said locking the mobile body with the refueling cartridge outside the reactor comprises:
locking the mobile body with the refueling cartridge in a new fuel depot;
the method further comprises the following steps:
the locked moving body and the refueling special sleeve are conveyed into a reactor hall; and
the locked mobile body and the refueling cartridge are transported into the reactor core.
9. A method for taking out a control rod assembly from a reactor core, wherein the control rod assembly comprises a moving body and an outer sleeve, and is characterized in that a first reserved vacancy and a second reserved vacancy are reserved in the reactor core, wherein a temporary storage sleeve for temporarily storing a refueling special tool is arranged in the first reserved vacancy; the method comprises the following steps:
providing a refueling special sleeve, wherein the moving body can be locked or unlocked with the refueling special sleeve in the refueling special sleeve;
providing a refueling special tool capable of being locked or unlocked with the outer sleeve and the refueling special sleeve within the outer sleeve and the refueling special sleeve, respectively;
locking the refueling specific tool with the refueling specific sleeve outside the reactor;
placing the locked refueling specific tool and the refueling specific sleeve at the second reserved void within the reactor core;
transferring the moving body into the temporary storage sleeve;
unlocking the special refueling tool and the special refueling sleeve;
transferring the refueling specific tool into the outer sleeve to be locked with the outer sleeve; and
removing the locked refueling specific tool and the outer sleeve out of the reactor.
10. The method of claim 9, further comprising, after unlocking the refueling specialized tool from the refueling specialized sleeve:
transferring the moving body into the refueling special sleeve to be locked with the refueling special sleeve; and
and moving the locked moving body and the refueling special sleeve out of the reactor.
11. The method of claim 9,
the structure of the temporary storage sleeve is the same as that of the outer sleeve.
12. The method of claim 10,
in the reactor, the transfer of the refueling special tool and the moving body, the unlocking of the refueling special tool and the refueling special sleeve, the locking of the refueling special tool and the outer sleeve and the locking of the moving body and the refueling special sleeve are realized through the cooperation of a refueling machine and a cock of the refueling system in the reactor.
13. The method of claim 9, wherein said locking the refueling specific tool with the refueling specific sleeve outside the reactor comprises:
locking the refueling specific tool with the refueling specific sleeve in a new fuel depot;
the method further comprises the following steps:
transporting the locked refueling special tool and the refueling special sleeve into a reactor hall; and
moving the locked refueling specific tool and refueling specific sleeve into the reactor core.
14. A method of replacing a control rod assembly, the control rod assembly including a traveling body and an outer sleeve, the method comprising:
the method of claim 10, removing the refueling specific tool and the spent outer sleeve from the reactor, and removing the spent mobile and the refueling specific sleeve from the reactor;
the method of claim 3, moving the new outer sleeve into a core operating position of the reactor core, and moving the new moving body into the new outer sleeve.
15. The method of claim 14,
and after all the outer spent sleeves and the spent moving bodies of the control rod assemblies are moved out of the reactor, the outer spent sleeves and the spent moving bodies are moved into the core working position of the reactor core.
16. The method of claim 14,
and after the outer depleted sleeve and the depleted moving body of each group of control rod assemblies are moved out of the reactor, moving the outer depleted sleeve and the depleted moving body into the 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 true CN113871041A (en) | 2021-12-31 |
| CN113871041B 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 (21)
| 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 |
| JPH11109071A (en) * | 1997-10-03 | 1999-04-23 | Toshiba Corp | High-speed breeder reactor and decomposition device of its reactor core upper mechanism |
| 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 |
| 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 |
| US20130044850A1 (en) * | 2011-08-19 | 2013-02-21 | Lewis A. Walton | 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 |
| 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 |
| US20190252082A1 (en) * | 2018-02-12 | 2019-08-15 | Westinghouse Electric Company Llc | Thermal sleeve |
| US20200365288A1 (en) * | 2019-05-15 | 2020-11-19 | Ge-Hitachi Nuclear Energy Americas Llc | Boiling water reactor blade guide and exchange tool |
| 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 |
-
2021
- 2021-09-26 CN CN202111129136.9A patent/CN113871041B/en active Active
Patent Citations (22)
| 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 |
| JPH11109071A (en) * | 1997-10-03 | 1999-04-23 | Toshiba Corp | High-speed breeder reactor and decomposition device of its reactor core upper mechanism |
| 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 |
| US20130044850A1 (en) * | 2011-08-19 | 2013-02-21 | Lewis A. Walton | Nuclear reactor refueling methods and apparatuses |
| 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 |
| 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 |
| 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 |
| US20190252082A1 (en) * | 2018-02-12 | 2019-08-15 | 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 |
| US20200365288A1 (en) * | 2019-05-15 | 2020-11-19 | Ge-Hitachi Nuclear Energy Americas Llc | Boiling water reactor blade guide and exchange tool |
| 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 |
|---|
| H.GROSS: "The BWR hybrid 4 control rod", NUCLEAR ENGINEERING AND DESIGN, vol. 108, no. 3, 31 August 1988 (1988-08-31), pages 433 - 436 * |
| 王浩仲;吴水金;杨孔雳;谷继品;苏喜平;夏凡;刘川川;: "分体式控制棒组件换料工艺路线设计", 科技创新导报, no. 19, pages 55 - 58 * |
| 王浩仲等: "一种分体式控制棒组件换料工艺路线设计", 科技创新导报, no. 19, pages 55 - 58 * |
| 苏喜平等: "CFR600堆芯组件自由跌落试验的冲击响应分析", 强度与环境, vol. 48, no. 3, 30 June 2021 (2021-06-30), pages 28 - 35 * |
| 莫***;方浩宇;陈训刚;颜达鹏;李长香;邓朝俊;牛昊轩;: "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", 中国核电, no. 03, 15 June 2020 (2020-06-15), pages 328 - 332 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN113871041B (en) | 2024-05-10 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN105355253A (en) | Method for transferring nuclear power station waste filter | |
| US4544521A (en) | Actuating device for two clusters of control rods movable vertically in one and the same fuel array of the core of a nuclear reactor | |
| CN104271378A (en) | System for locking / unlocking an object under a structure having a hook for drawing and supporting same | |
| US20150060705A1 (en) | System and method for transferring and/or working near a radioactive payload using shield-gate apparatus | |
| US20140272510A1 (en) | Structure for storing motor vehicle batteries having a mechanism for locking the batteries in the storage cells | |
| CN113871041A (en) | Control rod assembly mounting method, control rod assembly removing method and control rod assembly replacing method | |
| CN112863715A (en) | Rotary type material changing special structure for replacing control rod assembly moving body | |
| JP4256349B2 (en) | Nuclear reactor demolition and removal equipment, and demolition and removal method | |
| CN109887628A (en) | A kind of weary pond of PWR nuclear power plant and refuelling pool integrated apparatus | |
| EP3438991A1 (en) | Modular lower moving system for nuclear fuel handling and method of refueling nuclear fuel using the same | |
| CN112863716B (en) | A special structure of formula of pushing down reloading for changing control rod assembly moving body | |
| JPH0458911B2 (en) | ||
| CN108986940A (en) | Verification tool after a kind of maintenance of heavy water reactor spentnuclear fuel rod cluster grabbing tool | |
| CN113871043B (en) | Method for replacing outer sleeve of control rod assembly in reactor core | |
| US9903166B2 (en) | Receptacle for tubular drilling tools having different diameters | |
| CN115376713B (en) | Integrated reactor loading and reloading device, system and process | |
| CN218413995U (en) | Horizontal high-temperature gas cooled reactor structure | |
| JPS61162788A (en) | Inserter of locking tube for fuel aggregate | |
| CN110718311B (en) | A first mechanism is grabbed in reloading for lead-based reactor fuel assembly | |
| KR101969700B1 (en) | Nuclear reactor retubing assembly | |
| CN113871042B (en) | Material changing device for control rod assembly moving body | |
| EP1411529B1 (en) | Method for positioning nuclear fuel assemblies in a nuclear plant reactor core and installation for carrying out said method | |
| CN106663480A (en) | Method of extracting plug and removable unit when refueling nuclear reactor | |
| CN208488985U (en) | The underwater tripper that the highly dense screen work of Spent Fuel Pool dilatation lifts | |
| CN113077917A (en) | Radioactive sample transfer device and transfer system |
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 |