WO2000060607A1 - Procede de retrait de structure interne au coeur d'un reacteur - Google Patents

Procede de retrait de structure interne au coeur d'un reacteur Download PDF

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Publication number
WO2000060607A1
WO2000060607A1 PCT/JP1999/001678 JP9901678W WO0060607A1 WO 2000060607 A1 WO2000060607 A1 WO 2000060607A1 JP 9901678 W JP9901678 W JP 9901678W WO 0060607 A1 WO0060607 A1 WO 0060607A1
Authority
WO
WIPO (PCT)
Prior art keywords
cylindrical
internal structure
furnace
radiation shielding
radiation
Prior art date
Application number
PCT/JP1999/001678
Other languages
English (en)
Japanese (ja)
Inventor
Masataka Aoki
Norihito Saitou
Takahiro Adachi
Original Assignee
Hitachi, Ltd.
Hesco Technology Co., Ltd.
Icc Co., Ltd.
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi, Ltd., Hesco Technology Co., Ltd., Icc Co., Ltd. filed Critical Hitachi, Ltd.
Priority to JP2000610014A priority Critical patent/JP4177964B2/ja
Priority to PCT/JP1999/001678 priority patent/WO2000060607A1/fr
Publication of WO2000060607A1 publication Critical patent/WO2000060607A1/fr

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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
    • 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

Definitions

  • the present invention relates to unloading of reactor internal structures such as a core shroud installed in a reactor pressure vessel (hereinafter referred to as RPV) housed in a reactor building of a nuclear power plant.
  • RPV reactor pressure vessel
  • JP-A-8-233972, JP-A-8-152495, and JP-A-10-132985 There are things that are.
  • core structures such as the core shroud, upper lattice plate, core support plate, and jet pump are individually removed and replaced with new ones.
  • Japanese Patent Application Laid-Open No. 8-240693 discloses that the reactor internal structure is roughly cut in the RPV with the RPV and the reactor well filled with water, and the cut pieces are cut in the reactor well. It is further described that the shredder is cut into small pieces, packed in containers and transported out of the furnace. In this method, the furnace internal structure is cut in the furnace or in the equipment pool.
  • Japanese Patent Application Laid-Open No. 10-104389 describes a third conventional technique in which containers used for transportation and storage have a multi-layer structure. This is a transport and storage container on the premise that the above-mentioned furnace internal structure is cut in the furnace or in the equipment pool.
  • the external dimensions of the transport container (hereinafter, referred to as a cask) for storing the cut pieces are limited by the size of the equipment hatch installed on the operation floor of the reactor building S. For this reason, the capacity of the cask cannot be too large. In addition, since the size and shape of the cut pieces are various, the capacity of the cut pieces in the mask is about 30% on average.
  • An object of the present invention is to provide a method for carrying out a reactor internal structure that can reduce the working time when the reactor internal structure is carried out of a reactor building, and can improve the working efficiency associated therewith. Disclosure of the invention
  • a first feature of the present invention for achieving the above object is that the above-mentioned structure in which other reactor internal structures to be carried out other than the cylindrical internal structure surrounding the core disposed in the reactor vessel are contained.
  • the internal structure of the cylindrical furnace is covered with a radiation shield, and the internal structure of the cylindrical furnace is carried out of the reactor building together with the radiation shield.
  • a second feature of the present invention for achieving the above object is that a non-cylindrical internal structure other than the cylindrical internal structure is transported into a cylindrical internal structure surrounding a core disposed in a reactor vessel. Another internal structure to be put in is put in, the cylindrical internal structure is covered with a radiation shield, and the cylindrical internal structure is carried out of the reactor building integrally with the radiation shield.
  • multiple internal structures can be carried out of the reactor building at one time, so the internal structures are carried out more than the conventional method of carrying out internal structures.
  • the number of times can be reduced. Therefore, when removing the reactor internals from the reactor building, the work time can be shortened, and the work efficiency can be improved accordingly.
  • a third feature of the present invention for achieving the above object is that the cylindrical furnace internal structure containing other furnace internal structures to be carried out other than the cylindrical furnace internal structure is covered with a radiation shield.
  • a radiation shielding lid which is a part of the radiation shielding body is attached to the upper part of the cylindrical furnace internal structure, and the cylindrical furnace internal structure and the radiation shielding lid are lifted integrally.
  • the inner structure of the cylindrical furnace is connected to one of the radiation shields.
  • the radiation shielding lid and the cylindrical radiation shielding body are very easily attached to the cylindrical furnace internal structure by lifting the cylindrical internal structure together with the radiation shielding lid. Can be attached. Therefore, it is possible to reduce the time required to attach the radiation shield to the internal structure of the cylindrical furnace, and to improve the working efficiency associated therewith.
  • a fourth feature of the present invention for achieving the above object is that, when a radiation shield is attached to the furnace internal structure, a radiation shield which is a part of the radiation shield is provided above the furnace internal structure.
  • a lid is attached, a cylindrical radiation shield, which is a part of the radiation shield, is installed on the upper flange of the reactor vessel, and the radiation shield lid attached to the internal structure of the reactor is hung.
  • Raise put the furnace internals into the cylindrical radiation shield, place a part of the cylindrical radiation shield on the radiation shield lid, the radiation shield lid, the cylindrical radiation shield And the cylindrical furnace internal structure is integrally lifted, and a radiation shielding bottom lid is attached below the cylindrical radiation shielding body.
  • the radiation shielding lid, the cylindrical radiation shielding body, and the radiation shielding bottom The radiation shield comprising a lid and the furnace internal structure And as the integral is unloaded to the outside of the reactor Ken stars.
  • the radiation shielding lid and the cylindrical radiation shielding body can be very easily attached to the furnace internal structure.
  • the time required to attach the radiation shield to the internal structure of the cylindrical furnace can be shortened, and the work efficiency associated therewith can be improved.
  • a fifth feature of the present invention for achieving the above object is that a cylindrical furnace internal structure is provided.
  • the radiation shielding bottom is attached to the cylindrical radiation shielding body. Attach the lid.
  • the internal structure of the tubular reactor or the internal structure of the reactor can be covered with the radiation shield, it can be carried out of the reactor building.
  • FIG. 1 is a flowchart showing the work procedure of the first embodiment.
  • FIG. 2 is a longitudinal sectional view of a reactor building of a boiling water reactor to which the present invention is applied.
  • FIG. 3 is a longitudinal sectional view of a reactor pressure vessel of a boiling water reactor to which the present invention is applied.
  • FIG. 4 is a detailed diagram of step 105 in the first embodiment.
  • FIG. 5 is a detailed diagram of step 106 in the first embodiment.
  • FIG. 6 is a detailed diagram of step 107 in the first embodiment.
  • FIG. 7 is a detailed diagram of step 109 in the first embodiment.
  • FIG. 8 is a detailed diagram of step 110 in the first embodiment.
  • FIG. 9 is a detailed diagram of step 1 11 in the first embodiment.
  • FIG. 10 is a detailed view of steps 112 and 113 in the first embodiment.
  • FIG. 11 is a detailed diagram of steps 114 to 116 in the first embodiment.
  • FIG. 12 is a detailed diagram of steps 1117 to 119 in the first embodiment.
  • FIG. 13 is a detailed diagram of step 120 in the first embodiment.
  • FIG. 14 is a flowchart showing the working procedure of the second embodiment.
  • FIG. 15 is a detailed view of step 122 in the second embodiment.
  • FIG. 16 is a detailed diagram of step 122 in the second embodiment.
  • FIG. 17 is a detailed diagram of step 123 in the second embodiment.
  • FIG. 18 is a detailed diagram of step 124 in the second embodiment.
  • FIG. 19 is a detailed diagram of step 107a in the third embodiment.
  • FIG. 20 is a detailed diagram of steps 11 17 a and 11 18 a in the fourth embodiment.
  • FIG. 21 is a flowchart showing the working procedure of the fifth embodiment.
  • FIG. 22 is a view showing the internal structure of a reactor vessel of a pressurized water reactor to which the present invention is applied. BEST MODE FOR CARRYING OUT THE INVENTION
  • Example 1 of the present invention will be described.
  • a core shroud hereinafter simply referred to as a shroud
  • FIG. 2 is a cross-sectional view of a reactor building 4 near a reactor pressure vessel (hereinafter referred to as RPV) 1, which is a reactor vessel for carrying out a part of the reactor internal structure 2 in the present embodiment.
  • Reactor building 4 is the building in which RPV 1 is located.
  • Furnace structure 2 is the structure inside RPV 1.
  • Reactor building In the shop 4 there is a reactor containment vessel (hereinafter referred to as PCV) 3 below the operating floor 5, and RPV 1 is stored in PCV 3.
  • the reactor internal structure 2 including the shroud 11 is placed in the RPV 1, and the reactor well 6 above the RPV 1, the fuel pool 8 for storing fuel,
  • An equipment pool 7 is provided for temporary storage of furnace internals such as steam dryers.
  • a fuel exchange trolley 9 for exchanging fuel is provided on the operating floor 5, and a ceiling crane 10 is provided near the roof of the reactor building 4.
  • the ceiling crane 10 is a reactor pressure vessel lid (hereinafter referred to as RPV top head) 1a, and of the reactor internals 2, a steam dryer, steam-water separator and shroud head.
  • the main purpose is to lift items to be removed during periodic inspections.
  • the shroud 11 is disposed in the center of the RPV 1, and the shroud 11 is supported by a shroud support cylinder 12.
  • the shroud sabot cylinder 12 is supported on the bottom of the RPV 1 by a notch plate 28 and a shroud sabot leg 13.
  • an upper lattice plate 14 as an upper core support plate is provided at an upper portion, and a core support plate 15 as a lower core support plate is provided at a lower portion.
  • a control rod 20, a control rod guide tube 21, and a fuel assembly 22 are installed inside the shroud 11.
  • a jet pump 16 is provided between the shutter 11 and the RPV 1, and the jet pump 16 includes a jet pump inlet mixer 17, a jet pump riser 18 and a jet pump riser 18. It consists of a pump diffuser 19.
  • a steam dryer 24, a steam / water separator / shroud head 25, a guide rod 23 a, a feedwater sparger and piping 23 b, a core spray sprayer and piping 23 c is provided above the shroud. It has been concluded by the port through the ribs 47 that were provided. Below the shroud 11, equipment such as a core instrumentation guide tube 26 and an incore stabilizer 27 are provided below the shroud 11. In this embodiment, the reactor internals are carried out to a nuclear plant having such a configuration.
  • the shroud 11, the upper lattice plate 14, the core support plate 15, the jet pump 16, and the furnace internal structure 2 a to be unloaded (hereinafter referred to as unloaded material) 2 a
  • unloaded material 2 a Select the guide rod 23a, feed water sparger and piping 23b, and core spray sparger and piping 23c.
  • the flow chart in Fig. 1 shows the state in which the core support plate 15 is attached and the core support plate 15 and the shroud 11 of the unloading 2a are removed from the shroud 11
  • the shroud cutting device is installed in the space where the jet pump 16 was installed, cuts from the outside of the shroud 11, and the output 2a is a radiation shield (for example, carbon steel).
  • the container is enclosed in a transport container (hereinafter referred to as a cask) 52 composed of, and is carried out of the reactor building 4 by a crane installed outside the reactor building 4.
  • the cask 52 used in this embodiment includes a transport container top cover (hereinafter, referred to as an upper cover) 45, a transport container bottom cover (hereinafter, referred to as a bottom cover) 57, and a transport container body (hereinafter, referred to as a cask body).
  • a transport container top cover hereinafter, referred to as an upper cover
  • a transport container bottom cover hereinafter, referred to as a bottom cover
  • a transport container body hereinafter, referred to as a cask body.
  • step 101 the steam dryer 24 is carried out. Remove the RPV top head 1a and the steam dryer 24 from the RPV 1 by the ceiling clean 10, and move to the equipment pool 7. At this time, the reactor water level 67 is the position where the reactor well 6 is full. Then, in step 102, Separator 25 is unloaded. Remove the steam / water separator / head 25 using the ceiling crane 10 and move to the equipment pool 7. Next, in step 103, all fuel is carried out. All of the fuel assemblies 22 loaded in the core are taken out of the core using the refueling trolley 9 and moved to the fuel rack 30 installed in the fuel pool 8. Next, in step 104, the control rod 20 and the control rod guide tube 21 are unloaded.
  • FIG. 4 is a view showing a procedure for removing the upper lattice plate 15.
  • the reactor water level 67 is a position where the reactor well 6 is filled with water.
  • an iron plate 44 is laid on the core support plate 15. As shown in Fig. 5, an iron plate 44 is laid on the core support plate 15 below the shroud 11. By installing the iron plate 44, a container can be composed of the recirculation lid 11, the core support plate 15 and the iron plate 44, and the container is transported to this container in a later step. Object 2a can be inserted. By installing the iron plate 44, it is possible to prevent falling when the unloading material 2a is placed on the core support plate 15. Further, an effect of blocking radiation in a downward direction can be obtained.
  • FIG. 6 is a view showing a procedure for removing the jet pump 16.
  • the jet pump 16 is detached in three parts: a jet pump inlet mixer 17, a jet pump riser 18, and a jet pump diffuser 19.
  • a jet pump inlet mixer 17 removes the jet pump inlet mixer 17 and pass it between the RPV 1 and the upper shroud ring section 32 on the iron plate 44 inside the shroud.
  • the jet pump riser 18 is removed similarly to the jet pump inlet mixer 17, and the jet pump riser 18 is moved onto the iron plate 44.
  • the jet pump diffuser 19 is removed and moved onto the iron plate 44.
  • the jet pump 16 is installed
  • the gap between the RPV 1 and the shroud top ring 32 is narrow, about 300-400 mm, so that the maximum diameter of the jet pump diff unit is about 400-530 mm.
  • the 19 cannot be removed. Therefore, in this embodiment, as shown in Fig. 6, a part of the shroud upper ring portion 32 where the gap with the RPV 1 wall is narrow is cut out by a remote cutting device.
  • the notch 32b is provided.
  • the jet pump diffuser 19 is removed from the notch 32 b and moved onto the iron plate 44. Move the 20 jet diffusers 19 sequentially in the circumferential direction and remove them from the cutouts in the upper shroud ring 32.
  • the cutout portion 32b is provided at one place on the circumference of the shroud upper end ring portion 32, but may be provided at a plurality of places. This allows the jet pump diffuser 19 to be moved into the shroud 11 before the shroud 11 is cut from the RPV 1.
  • the jet pump 16 can be carried out together with the shutter 11. Therefore, the number of times of unloading can be reduced as compared with the case where the jet pump 16 is unloaded separately from the shutter 11.
  • step 108 of the unloading material 2a, other than the shroud 11, the upper grid plate 14, the core support plate 15, and the jet pump 16, other than into the shroud 11.
  • a part of the unloading 2a such as a part of the unloading 2a that was moved to the equipment pool in step 105, other than the shroud 11, upper grid plate 14, core support plate 15, and jet pump 16 a is moved onto the core support plate 15 and the iron plate 44 in the shroud 11.
  • FIG. 7 is a schematic diagram for cutting the shroud 11. As shown in Fig. 7 (a) and (b), the shroud cutting device 40 and the guide rail 1 for the shroud cutting device are newly installed on the space where the jet pump was installed. I do.
  • FIG. 7 (b) is a diagram showing the details of the part C in FIG. 7 (a).
  • the shroud cutting device 40 travels on a guide rail 41 laid all around on a baffle plate 28 between the shroud 11 and the RPV 1, and is cut by electric discharge machining. 4 Cut 2 from outside of the shadow.
  • electric discharge machining not only electric discharge machining but also other cutting means such as machining, high pressure water jet and the like may be used.
  • Step 109 is performed in the following procedure.
  • the guide rail 41 is laid on the baffle plate 28.
  • the shroud cutting device 40 is installed on the guide rail 41.
  • the shroud 11 is suspended by the ceiling crane 10 to prevent the shroud 11 from falling or falling off during cutting.
  • the cut portion 42 is cut using the shroud cutting device 40.
  • several cutting sub-blocks 43 are sequentially inserted into the cutting opening, so that the cut surface of the shroud is kept horizontal and the remaining The cutting part can be easily cut.
  • the shroud 11 is temporarily placed on the shroud cylinder 12 and cut off from the ceiling crane 10.
  • the core support plate 15 can be carried out together with the shroud 11. So, as mentioned in step 106, the core Place the output 2a on the support plate 15 and remove it together with the shroud 11
  • core support plate 15 is shrouded.
  • the number of times of unloading can be reduced compared to the case of unloading separately from 11. Further, by cutting the shroud 11 from the outside of the shroud 11, the shroud 11 is cut at a position below the core support plate without removing the core support plate 15. be able to.
  • Steps 108 and 109 may be performed in the reverse order.
  • FIG. 8 is a view showing a procedure for moving the upper lattice plate 14.
  • the upper lattice plate 14 temporarily placed in the equipment pool 7 in step 105 is moved to the mounting portion of the upper lattice plate 14 in the shroud 11.
  • Fig. 8 (b) shows the details of section F in Fig. 8 (a).
  • the upper lattice plate 14 was removed in step 105, it was fixed by wedges 34, etc., but when it is carried out after this step, the upper lattice plate 14 is fixed by its own weight. Is enough. Therefore, as shown in FIG. 8 (b), the upper lattice plate 14 is placed on the upper ring portion 32. If it is necessary to fix the upper lattice plate 14 in consideration of shaking during unloading, etc., use the wedge 34 or L-shaped strip again.
  • Step 110 is performed after Step 108. According to this step, it is possible to move to the mounting portion of the upper lattice plate 14 in the shroud 11. Thereby, the upper lattice plate 14 can be carried out together with the shroud 11. For this reason, the number of times of unloading can be reduced as compared with the case where the upper lattice plate 14 is unloaded separately from the chassis 11. Wear.
  • FIG. 9 is a view showing a procedure for attaching the upper cover 45 to the upper part of the shroud 11.
  • Fig. 9 (a) attach the upper lid 45 to the shroud upper ring 32.
  • the reactor water level 67 is changed from the position where the reactor water level 67, which is the reactor water level 67 up to step 110, is full, as shown in Fig. 9. Change to keep it at the top of RPV flange 29. This makes it possible to easily perform the work in the reactor well 6 in step 1 14.
  • Fig. 9 (b) shows the details of section G in Fig. 9 (a).
  • the upper lid 45 is fixed to the upper shroud ring 32 by the port 48 using the rib 47 attached to the upper shroud ring section 32 of the shroud.
  • the upper lid 45 has a two-stage structure having a convex portion on the upper surface.
  • the upper lid 45 serves as an upper lid of a cask 52 for integrally storing the shadow 11 formed after this step.
  • the upper part 49 of the two-step structure of the upper lid 45 has a slope on the side surface so that it can easily enter the cask body part 82, which is a part of the cask 52, in a later step. I have.
  • the upper part 49 is provided with a hanger 46 used to carry out the shroud 11. Providing the upper lid 45 with the hanging tool 46 allows the upper lid 45 and the hanging tool 46 to be provided in a single mounting operation. Therefore, when the shroud 11 is carried out, there is no need to provide a new hanging device on the shroud 11, and the shroud 11 can be easily replaced. Unloading can be carried out.
  • Steps 11 and 12 the crane 50 is installed, and in Step 113, the carry-out opening 55 is set.
  • a crane 50 is installed outside the reactor building 4, and a temporary opening 55 for carrying out the mask body 82 is set on the roof of the reactor building 4.
  • a switchgear 51 that can be freely opened and closed will be installed in the temporary opening 55.
  • the temporary opening 55 is provided above the RPV 1 and the size is the size of the cask body 82 to be carried in, the size of the hanging jig for carrying out the cask 52, the cask body 82 when loading and the cask. 5 2 Decide in consideration of shaking during unloading.
  • the installation of the switchgear 51 that can be opened and closed can take measures against rainwater and negative pressure in the reactor building 4 during work. Note that the installation of the lifting machine 50 in step 1 12 and the setting of the temporary opening 55 for unloading in step 113 can be performed at any stage before the loading of the cask body 82 in step 114. You may go.
  • FIG. 11 is a diagram showing a series of flows when the shroud 11 is carried into the cask body portion 82.
  • the cask body 82 is loaded by the lifting machine 50 and temporarily placed in the upper flange 29 of the RPV.
  • the cask trunk 82 has a concentric cylindrical triple structure. This concentric cylindrical triple structure is based on the following reasons. In other words, the reactor internal structure 2 such as the shadow 11 stored in the cask body 8 2 is activated, and the radiation on the surface of the cask body 8 2 is necessary to carry it out of the reactor building 4.
  • the dose rate must be 1 Om SVZ hr or less specified in the on-site transport standards.
  • the cask shell 82 must have a wall thickness of about 300 to 400 mm when the material is carbon steel. Forming and manufacturing a mask with a thickness of 300 to 400 mm in one piece is better than manufacturing a thin-walled mask body 53 with a thickness of 100 to 150111111. It is difficult and the production cost is extremely high. Therefore, by stacking two to three thin cask trunks 53 having a thickness of 100 to 150 mm, a cask trunk 82 having a required thickness is obtained. In this embodiment, three thin cask body portions 53 having different inner diameters and having a thickness of 150 are overlapped with each other to obtain a cask body portion 82 having a thickness of 450 mm.
  • cask body 82 With such a concentric cylindrical double-layered structure, it is possible to obtain a cask body 82 that is inexpensive and has the same shielding ability as a thick wall. If the casks that can reduce the radiation dose rate on the surface of the cascade body to a level below the radiation dose rate stipulated in the on-premise transport standards can be manufactured as an integral structure, use: Is also good. In addition, not only the cask trunk 82 but also members requiring radiation shielding ability may use the same double-layered structure as necessary.
  • An upper lid opening 52 a into which the upper step 49 can be inserted is provided on the upper surface of the cask trunk 82. As shown in FIG. 11 (a), the inner surface of the upper lid opening 52a is provided with a slope for fitting with the slope of the side surface of the upper step 49. As shown in FIG. 11 (a), the inner surface of the upper lid opening 52a is provided with a slope for fitting with the slope of the side surface of the upper step 49. As shown in FIG.
  • step 1 preparation for lifting the shroud 11 1 is performed.
  • the wire 56 from the hoisting machine 50 is attached to the hanging tool 46 through the upper lid opening 52a to prepare for lifting the shroud.
  • step 1 16 the shroud 11 is lifted.
  • the top lid 45 is lifted together with the shutter 11 by the hoisting machine 50, and the cask trunk is lifted as shown in Fig. 11 (c).
  • the fitting portion between the top cover 45 and the cask body 82 needs to be tightly fitted.
  • the fitting can be made dense.
  • the hoist 50 and the cask body 82 are connected by wire 70 by remote control.
  • the cask body 82 is attached to the upper lid 45 without removing the wire 56 attached to the upper lid 45 to remove the shroud 11 and the upper lid 45 from the RPV 1. be able to.
  • the work time required for mounting the cask 52 can be reduced.
  • the upper cover 45 and the cask body 82 can be handled as one body without mechanically fastening by a port or the like. . Thereby, the number of man-hours can be reduced as compared with the case of performing mechanical fastening.
  • the cask trunk 82 is temporarily placed on the upper flange 29 of the RPV, and the shroud 11 is loaded into the cask trunk 82 from within the RPV 1, whereby the shroud 11 1 Can be carried into the cask body 82 without opening the side of the cask body from the one having the shielding ability (both the RPV 1 and the cask body 82 have the shielding ability).
  • the radiation dose to the reactor building when the shroud 11 is carried into the cask body 82 from the RPV 1 can be suppressed.
  • step 117 the rails 58 and the cart 59 are set. No.
  • FIG. 1 2 is a diagram showing a series of flows when the bottom lid 57 is attached to the cask body 82 and then the cask 52 is carried out of the reactor building 4. No.
  • step 118 the bottom cover 57 is attached.
  • the carriage 59 with the bottom cover 57 is moved to the lower center of the cask body 82.
  • the cascade body 82 lifted by the hoist 50 is lowered to approach the bottom lid 57.
  • the cask body 82 is further lowered, and the bottom cover 57 is attached to the lower portion of the cask body 82.
  • the connection between the cask trunk 82 and the bottom lid 57 is made airtight using a metal 0-ring.
  • the shroud 11 can be stored in the cask 52 constituted by the top cover 45, the cask trunk portion 82, and the bottom cover 52. Further, by attaching the cask 52 to the shroud 11 in the air, the drainage of the cask 11 required when the cask 52 is installed in the water is not required. Therefore, the number of processes can be reduced.
  • step 1 19 the cask 52 is lifted and carried out.
  • the cask 52 is lifted by the crane 50 and carried out of the reactor building 4 through the temporary opening 55.
  • step 120 the cask 52 is stored in the storage.
  • a vertical underground storage 63 is placed near the reactor building 4, and the cask 52 carried out of the reactor building 4 is hung while the lifting machine 50 Is turned to the direction of the storage 63, and is carried into the storage 63. After carrying in, the storage 63 is closed, and the storage 63 is sealed.
  • the cask 52 may be loaded on a trailer and transported to a storage located far away.
  • the storage 63 may be provided in a building connected to the reactor building 4 and the building.
  • a plurality of reactor internal structures can be transported to the outside of the reactor building at a time by putting the reactor internal structures into the shroud and transporting them together. It is possible to reduce the number of times of carrying out the furnace internal structure as compared with the method of carrying out the furnace internal structure. Therefore, it is possible to shorten the work time required to carry out the reactor internals from the reactor building. In addition, the number of casks used when unloading the reactor internals from the reactor building can be reduced. Also, when the shroud 11 is stored in the cask 52, the shroud 11 is lifted into the cask body 8 2 installed on the upper flange 29 of the RPV, whereby the shroud 11 is lifted.
  • the radiation dose to the reactor building interior can be reduced as compared with the case where the gas is once taken out of the RPV 1 and then moved into the mask 52.
  • the method for loading the shroud 11 into the cask body 82 by lifting the shroud 11 inside the cask body 82 set in the upper flange 29 of the RPV is described below.
  • the present invention can also be applied to a case where a radiation shield is attached to a reactor internal structure carried out of a reactor vessel, and the same effects as those of the present embodiment can be obtained. In particular, it is recommended to use this method when carrying out multiple furnace structures as a single unit.
  • Example 2 the core support plate was once removed from the inside of the shroud, and the shroud was cut from the inside.
  • FIG. 14 shows a flowchart of the second embodiment.
  • Steps 121 to 126 of this embodiment will be described.
  • the reactor water level 67 is a position where the reactor well 6 is filled with water.
  • FIG. 15 shows the procedure for removing the core support plate 15.
  • Fig. 15 (a) remove the core support plate 15 installed at the lower part of the shroud 11 and move it to the equipment pool 7.
  • Fig. 15 (b) shows the details of part B of Fig. 15 (a).
  • the core support plate 15 is fixed to a lower flange 36 which is a step portion below the shroud 11 via a stud bolt 39 and a nut 38a.
  • the U-shaped cap 38 covering the nut 38a is fixed to the end of the stud port 39 by a weld 38b.
  • the welded portion 38b was cut off by remote control, the nut 38a and the stud port 39 fixed to the shroud 11 were removed, and the core support plate 15 was ceiling-clamped. Lift in lane 10 and move to equipment pool 7.
  • Fig. 16 shows the procedure for removing the core instrumentation guide tube 26 in the reactor.
  • the upper part of the in-core nuclear instrumentation guide tube 26 and the incore stablizer 27 are cut off, removed from the RPV 1, and moved to the equipment pool 7.
  • the shroud 11 and the shroud cylinder 12 When the position of the welding line is higher than the position of the incore stabilizer 27, the in-core core instrumentation guide tube 26 may be cut off while the existing incore stabilizer 27 is left.
  • FIG. 17 is a schematic diagram for cutting the shadow 11.
  • a rail receiving plate 76, a rail support 77, a guide rail 78 and a cutting device 75 are newly added to the lower flange 36.
  • FIG. 17 (b) is a diagram showing details of a portion D in FIG. 17 (a).
  • the shroud cutting device 75 runs on guide rails 78 installed around the entire circumference, and is set between the shroud 11 and the shroud support cylinder 12 by electric discharge machining. Cut the cut part 4 2 from the inside of the shroud 11.
  • electric discharge machining not only electric discharge machining but also other cutting means such as machining, high-pressure water jet method and the like may be used.
  • Steps 1 and 2 are performed in the following procedure.
  • the rail receiving plate 76, the rail support 77, the guide rail 78, and the cutting device 75 are mounted on the lower flange 36.
  • the shroud 11 is suspended from the ceiling crane 10 to prevent the shroud 11 from being inclined or falling off during cutting.
  • the cut portion 42 is cut using the shroud cutting device 75.
  • several cut-out openings 43 are sequentially inserted into the cutting opening to keep the cut surface of the shroud horizontal and cut the remaining non-cut part. make it easier.
  • the shadow 11 is temporarily placed on the shadow support cylinder 12 and separated from the ceiling crane 10.
  • the shroud 11 is removed from a position below the core support plate 15 before removing the jet pump 16. Wood 11 can be cut.
  • no other unloaded material 2a enters the shroud, so that the shroud weight can be reduced when the cutting is advanced. This makes it easier to lift by the ceiling crane 10 during cutting compared to the case where the other unloading material 2a is in the shroud, and also allows the shroud 11 to be cut during cutting. Deflection can be easily stabilized.
  • the core support plate 15 is moved. FIG.
  • FIG. 18 is a schematic diagram for moving the core support plate 15.
  • an iron plate 44 is laid on the core support plate 15 temporarily placed in the equipment pool 7, and the core support plate 15 is connected to the in-furnace shroud 11 Move in.
  • Fig. 18 (b) shows the details of section E in Fig. 18 (a).
  • the core support plate 15 was fixed by the U-shaped cap 38 when it was removed in step 122, but when it is carried out after this step, the core support plate 15 is not used. A fixation with a weight of 15 is sufficient. Therefore, the core support plate 15 is placed on the lower flange 36 as shown in Fig. 18 (b). If it is necessary to fix the core support plate 15 in consideration of shaking during unloading, etc., the core support plate 15 may be fixed again with the stud port 39, the nut 38a, etc. Alternatively, it may be fixed by some new fixing method.
  • step 125 the jet pump 16 is removed, and in step 126, the shroud 11, upper lattice plate 14, and core support of the conveyed material 2a are removed. Carry anything other than plate 15 into shroud 11. Steps 125 and 126 are exactly the same as steps 107 and 108 of the first embodiment, respectively, and thus description thereof is omitted here. In addition, If it is not necessary to remove the pump, steps 125 can be omitted.
  • the shroud can be cut from the inside of the shroud 11. Therefore, there is no need to install a cutting device in a narrow portion between the shutter 11 and the RPV 1, and the shroud 11 can be easily cut. Also, once the core support plate 15 is removed, the in-core nuclear instrumentation guide tube 26 and the incore stabilizer 27 below the core support plate 15 can also be removed. Also, as shown in Fig. 17, when the shroud 11 is cut off, there is no carry-out 2a in the shroud 11 so that the shroud 11 Can be easily lifted.
  • Embodiment 3 is an embodiment in which a notch is not provided in the upper ring portion of the shroud when the jet pump is removed.
  • This embodiment is different from the first embodiment in that the process performed in step 107 of FIG. 1 is changed to the following step 107a.
  • Other procedures are the same as those in the first embodiment, and the description is omitted here.
  • Step 107a of this embodiment will be described.
  • step 107 a remove the jet pump 16.
  • the jet pump 16 is detached in three parts: a jet bomb inlet mixer 17, a jet pump riser 18, and a jet pump diffuser 19.
  • FIG. 19 is a schematic diagram for removing the jet pump diffuser 19. The removal of the jet pump inlet mixer 17 and the jet pump riser 18 are performed in the same manner as in step 107, and therefore the description is omitted here.
  • the jet pump diffuser 19 is compressed and thinned by a remote compression device, and the jet pump diffuser 19 is compressed by the narrow space between the RPV 1 wall and the shroud top ring 32. Remove the pump diffuser 19 and move it onto the iron plate 44. Since the thickness of the jet pump diffuser 19 is about 9 mm, it is easy to compress with a remote compression device.
  • the 20 jet pump diffusers 19 are sequentially compressed and taken out from the narrow space between the RPV 1 wall and the shroud upper end ring 32. In order to make the jet pump diffuser 19 large enough to pass through the narrow space between the RPV 1 wall and the shroud upper ring 32, a remote cutting device was used. The pump diffuser 19 may be cut off. Also, both a remote compression device and a remote cutting device may be used.
  • the same effects as those of the first embodiment can be obtained.
  • the jet pump 16 when the jet pump 16 is removed, no cutout is formed in the shroud upper end ring portion 32. No foreign matter or gas is generated. This can prevent pollution of the reactor water due to foreign matter diffusion into the reactor water and contamination of the space above the operation floor by the gas.
  • the remote compression device is a simple device compared to the remote cutting device, the device contaminated by removing the jet pump 16 can be reduced.
  • the fourth embodiment is an embodiment in which the bottom cover 57 is attached to the cask body portion 82 and the inside of the cask 52 is sealed in the furnace water.
  • This embodiment is different from the first embodiment in that each of the steps performed in steps 11, 11 18, and 11 in FIG. 1 is performed in steps 11 a, 1 18 a, and 11 1 shown below. 9a. Other procedures are examples The description is omitted here because it is the same as 1.
  • Steps 117a to 119a the reactor water level 67 is the position where the reactor well 6 becomes full.
  • step 1 17a of the present embodiment will be described.
  • FIG. 20 is a diagram showing a flow when the bottom cover 57 is attached to the cask trunk 82.
  • a rail 58 on which a carriage 59 carrying a bottom cover 57 of the cask body 82 is laid is placed in the reactor well 6 and the equipment pool 7.
  • the bottom cover 57 used in this embodiment is provided with a drain hole (not shown) for draining water.
  • the shroud 11 and the cask trunk 82 are lifted to the reactor well 6 by the hoist 50.
  • rails 58 are laid in the reactor well 6 and the equipment pool 7.
  • a trolley 59 with a bottom lid 57 is placed on the rail.
  • a jack is provided between the cart 59 and the bottom cover 57 to adjust the level of the bottom cover 57.
  • step 1 18a the bottom cover 57 is attached.
  • the carriage 59 on which the bottom cover 57 is placed is moved to the lower center of the cask body 82.
  • the cask body 82 lifted by the hoist 50 is lowered to approach the bottom lid 57.
  • the cask is further lowered, and the bottom cover 57 is attached to the lower portion of the cask body 82.
  • the connection between the body of the cask body 82 and the bottom cover 57 is made airtight using a metal 0-ring or the like.
  • step 1 19 a the cask 52 is lifted and carried out.
  • the cask 52 is lifted until the bottom lid 57, which is a part of the cask 52, is above the reactor water level, and remains inside the cask 52 from the drain hole. Wait for the reactor water to drain. After draining is completed, close the drain hole.
  • the shroud 11 has the upper lid 45, the cask trunk 82 and It is shielded by a cask 52 composed of a bottom cover 52 and a bottom cover 52. In this state, the degree of surface contamination of the cask body 82 is measured and a contamination inspection is performed.
  • the cask 52 is lifted by the hoist 50 and carried out of the reactor building 4. After unloading, close switchgear 51.
  • the same effects as those of the first embodiment can be obtained. Furthermore, in this embodiment, when storing the shroud 11 in the cask 52, the bottom lid 57 is attached to the cask body 82 in water, so that the shroud 11 is also installed in the reactor building as in the first embodiment. Radiation dose can be reduced.
  • the jet pump 16 is removed from the reactor building 4 after being transported out of the reactor building 4, and the jet pump 16 is placed in a dedicated disk and transported out of the reactor building 4.
  • This embodiment is different from Embodiment 2 in that step 1 25 in FIG.
  • step 1 26 The process performed in step 1 26 is referred to as step 1 26 a shown below.
  • FIG. 21 shows a flowchart of this embodiment. Step 126a,
  • Steps other than 127 and 128 are the same as those in the second embodiment, and a description thereof will be omitted. Steps 126a, 127 and 128 of this embodiment will be described.
  • step 1 26a of the unloading 2a, other than the shroud 11, the upper lattice plate 14, the core support plate 15, and the jet pump 16 are carried into the shroud 11.
  • Shroud 11, upper lattice plate 14, core support plate among the unloading material 2 a that had been moved to the equipment pool in step 105 Move anything other than 15 and jet pump 16 onto core support plate 15 and iron plate 44 in shroud 11.
  • step 1 27 will be described.
  • step 127 remove the jet pump. Remove Jet Pump Inlet Mixer 17 and move to Equipment Pool. Next, remove jet pump riser 18 and move to the equipment pool. Next, remove the jet pump diffuser 19 and move it to the equipment pool.
  • the jet pump 16 is removed in the same manner as in step 125 of the second embodiment, except for the jet pump inlet mixer 17, the jet pump riser 18, and the jet pump diffuser 1. In this example, since the shroud 11 was already carried out at the stage of performing the step 127, the jet pump 16 was carried out. There are no narrow places.
  • the jet pump 16 is carried out.
  • the jet pump 16 is put in a special cask (not shown) in the equipment bull 7, and is carried out of the reactor building 4 and carried into the storage facility.
  • the same effects as those of the first embodiment can be obtained. Further, in the present embodiment, since the jet pump 16 is taken out after the shroud is carried out, when the jet pump 16 is taken out, the ejection of the jet pump 16 is obstructed. There is no narrow place. Therefore, ejection of the jet pump 16 can be easily performed.
  • Example 6 is an example in which the present invention is applied to a pressurized water nuclear power plant when an upper core structure and a lower core structure, which are internal structures of a reactor, are carried out of a reactor building. is there.
  • the structure of the reactor used for the pressurized water nuclear power plant will be described with reference to FIG.
  • a reactor core 102 is disposed at the center, and a fuel assembly 103 is disposed inside the reactor core 102.
  • the reactor core 102 is a tubular reactor structure surrounding the reactor core arranged in the reactor vessel 101.
  • An upper core support plate 107 is detachably installed on the upper end of the core tank 102.
  • the upper core plate 106 is disposed in the core tank 102 and is attached to the upper core support plate 107 by a plurality of upper core support columns 113.
  • the upper core plate 106, the upper core support plate 107, the control rod clusters 108 and the upper core support columns 113 constitute the upper core internal structure 110 together.
  • a lower supporting core plate 104 and a lower core plate 105 are provided below the core 102.
  • the core 102, the lower core support plate 104, and the lower core plate 105 together constitute a lower core internal structure 111.
  • the upper reactor internal structure 110 and the lower reactor internal structure 111 can be taken out of the reactor vessel 101 separately or together when they are connected to each other.
  • an example will be described in which the upper furnace internal structure 110 and the lower furnace internal structure 111 are separately carried out.
  • the upper cover 109 of the reactor vessel is removed, then the upper internal structure 110 is removed, and all the fuel assemblies 103 in the core are moved to the fuel pool.
  • the removed upper internal structure 110 is returned to the reactor vessel 101.
  • the upper reactor internal structure 1 1 10 and the lower reactor internal structure 1 1 1 1 1 Separately, attach the top cover, cask body and bottom cover according to the procedure shown in Fig. 9, Fig. 11 and Fig. 12, and use the cask consisting of the top cover, cask body and bottom cover to install the upper furnace. It covers the structure 110 (or the lower furnace internal structure 111).
  • Each of the above-mentioned parts constituting the mask is made of a radiation shielding material.
  • the cask With the upper reactor internal structure 110 (or the lower reactor internal structure 111) built in, the cask is unloaded outside the reactor building using the lifting machine 50 shown in Fig. 10. You. The cask is carried out of the reactor building outside through the opening, and is carried into the storage provided outside the reactor building.
  • the upper lid is attached to the upper flange 1 17 of the reactor core by a crane 50.
  • the cask body is placed on the upper flange 1 1 2 of the reactor vessel using the lifting machine 50.
  • the hoisting machine 50 lift the upper lid attached to the lower furnace internal structure 1 1 1 1 and put the upper end of the cask body on the upper lid as shown in Fig. 11 (c).
  • the lower furnace internal structure 1 1 1 is in the cask shell. This is further lifted and a bottom cover is attached to the lower end of the cask body.
  • the lower furnace internal structure 1 1 1 1 is stored in the cask constituted by the cask body, the upper lid and the bottom lid.
  • the cask is taken out of the reactor building outside through the opening, and is carried into the storage provided outside the reactor building.
  • the cut pieces may be carried out together with the lower furnace internals by the following procedure. That is, the lower furnace internal structure 1 1 1 has an inner space formed inside the core 10 2 and above the lower core plate 105. It is also possible to put a cut piece of the furnace internal structure into the inner space of the core 102 and carry it out together with the lower furnace internal structure 1 1 1. If necessary, take measures to prevent the steel plate from falling on the lower core plate 105. In addition, if there is a space in the upper furnace internal structure 110 where similar vessel-shaped objects or cut pieces are to be placed, place the cut pieces 122 in the space and place the upper furnace internal structure 110 in the space. It may be carried out together with 10.
  • an upper lid is attached to the upper end of the upper furnace internal structure 110, and the upper furnace internal structure 110 and the lower furnace internal structure 111 are integrally lifted up in the cask body, and then lifted. Then, a bottom lid may be attached to the lower end of the cask body, and these reactor internal structures may be stored in a single cask and transported outside the reactor building.
  • the mask can be easily attached to the upper furnace internal structure and the lower furnace internal structure.
  • man-hours can be reduced and work time can be reduced.
  • the cask trunk is temporarily placed on the upper flange 1 1 2 of the reactor vessel, and the reactor internals are loaded into the cask trunk from the reactor vessel. This makes it possible to reduce the radiation dose to the inside of the reactor building as compared with the case where the reactor internals are once taken out of the reactor vessel and then moved into the cask.
  • there are cut pieces of the furnace internals they can be placed in the same cascade as the furnace internals and carried out, thus reducing man-hours compared to the case of separately transporting the cut pieces.
  • the inner furnace structure constituting the lower inner furnace structure 1 1 1 1 The present invention may be applied to a reactor core 102, which is one of the products, as a tubular reactor internal structure.
  • the upper core support plate 1 17, which is one of the upper core internal structures 110 has a concave cross section
  • the present invention may be applied.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Ce procédé de retrait d'une structure interne au coeur d'un réacteur se caractérise par le fait que cette structure à retirer, autre qu'une structure cylindrique interne au coeur de réacteur enveloppant un coeur de réacteur installé dans la cuve d'un réacteur, est placée dans cette même structure cylindrique interne au coeur de réacteur, la structure cylindrique interne au coeur de réacteur résultant étant recouverte par un blindage de protection contre le rayonnement et étant retirée avec ce blindage de protection contre le rayonnement d'une construction logeant le réacteur nucléaire.
PCT/JP1999/001678 1999-03-31 1999-03-31 Procede de retrait de structure interne au coeur d'un reacteur WO2000060607A1 (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
JP2000610014A JP4177964B2 (ja) 1999-03-31 1999-03-31 炉内構造物の搬出方法
PCT/JP1999/001678 WO2000060607A1 (fr) 1999-03-31 1999-03-31 Procede de retrait de structure interne au coeur d'un reacteur

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/JP1999/001678 WO2000060607A1 (fr) 1999-03-31 1999-03-31 Procede de retrait de structure interne au coeur d'un reacteur

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WO2000060607A1 true WO2000060607A1 (fr) 2000-10-12

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WO (1) WO2000060607A1 (fr)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010008303A (ja) * 2008-06-30 2010-01-14 Hitachi-Ge Nuclear Energy Ltd 炉内構造物の搬出方法
JP2011090011A (ja) * 2010-12-28 2011-05-06 Hitachi-Ge Nuclear Energy Ltd 炉内構造物の搬出方法

Citations (7)

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Publication number Priority date Publication date Assignee Title
JPH08240693A (ja) * 1995-03-02 1996-09-17 Hitachi Ltd 原子炉圧力容器内構造物の撤去方法および切断方法
JPH08285997A (ja) * 1995-04-14 1996-11-01 Ishikawajima Harima Heavy Ind Co Ltd 原子炉圧力容器取替時の遮蔽方法
JPH09269392A (ja) * 1996-03-30 1997-10-14 Toshiba Corp 炉心シュラウドの据付方法および原子炉圧力容器内の放射線遮蔽構造
JPH1039077A (ja) * 1996-07-24 1998-02-13 Ishikawajima Harima Heavy Ind Co Ltd 原子炉圧力容器搬出及び搬入方法
JPH1039076A (ja) * 1996-07-24 1998-02-13 Ishikawajima Harima Heavy Ind Co Ltd 原子炉圧力容器搬出方法
JPH10111385A (ja) * 1996-10-03 1998-04-28 Hitachi Ltd 原子炉圧力容器内機器の取扱方法
JPH10132985A (ja) * 1996-10-31 1998-05-22 Toshiba Corp 炉内構造物の交換方法

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH08240693A (ja) * 1995-03-02 1996-09-17 Hitachi Ltd 原子炉圧力容器内構造物の撤去方法および切断方法
JPH08285997A (ja) * 1995-04-14 1996-11-01 Ishikawajima Harima Heavy Ind Co Ltd 原子炉圧力容器取替時の遮蔽方法
JPH09269392A (ja) * 1996-03-30 1997-10-14 Toshiba Corp 炉心シュラウドの据付方法および原子炉圧力容器内の放射線遮蔽構造
JPH1039077A (ja) * 1996-07-24 1998-02-13 Ishikawajima Harima Heavy Ind Co Ltd 原子炉圧力容器搬出及び搬入方法
JPH1039076A (ja) * 1996-07-24 1998-02-13 Ishikawajima Harima Heavy Ind Co Ltd 原子炉圧力容器搬出方法
JPH10111385A (ja) * 1996-10-03 1998-04-28 Hitachi Ltd 原子炉圧力容器内機器の取扱方法
JPH10132985A (ja) * 1996-10-31 1998-05-22 Toshiba Corp 炉内構造物の交換方法

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010008303A (ja) * 2008-06-30 2010-01-14 Hitachi-Ge Nuclear Energy Ltd 炉内構造物の搬出方法
US8411813B2 (en) 2008-06-30 2013-04-02 Hitachi-Ge Nuclear Energy, Ltd. Method for carrying out reactor internal
JP2011090011A (ja) * 2010-12-28 2011-05-06 Hitachi-Ge Nuclear Energy Ltd 炉内構造物の搬出方法

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