WO2019208062A1 - Method for dismantling nuclear reactor containment vessel and biological shielding wall - Google Patents

Method for dismantling nuclear reactor containment vessel and biological shielding wall Download PDF

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Publication number
WO2019208062A1
WO2019208062A1 PCT/JP2019/012556 JP2019012556W WO2019208062A1 WO 2019208062 A1 WO2019208062 A1 WO 2019208062A1 JP 2019012556 W JP2019012556 W JP 2019012556W WO 2019208062 A1 WO2019208062 A1 WO 2019208062A1
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Prior art keywords
dismantling
shielding wall
pcv
bsw
containment vessel
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PCT/JP2019/012556
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French (fr)
Japanese (ja)
Inventor
永江　良明
賢治 木尾
竜也 飯塚
徳雄 清水
森　幸夫
潤也 田畑
北原　隆
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株式会社日立プラントコンストラクション
日立Ｇｅニュークリア・エナジー株式会社
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Publication of WO2019208062A1 publication Critical patent/WO2019208062A1/en

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing

Definitions

  • the present invention relates to a dismantling method for a nuclear reactor containment vessel (hereinafter sometimes simply referred to as PCV (Primary Continent Vessel)) and a biological shielding wall (hereinafter simply referred to as BSW (Biological Shield Wall)).
  • PCV Primary Continent Vessel
  • BSW biological shielding wall
  • FIG. 16 is a cross-sectional view showing an example of a main part of the reactor building.
  • a PCV 12 is formed in the reactor building 10, and a reactor pressure vessel (hereinafter simply referred to as RPV (Reactor Pressure Vessel)) 14 is installed in the PCV 12.
  • RPV reactor Pressure Vessel
  • An in-furnace structure 15 is attached inside the RPV 14.
  • RSW Heat shielding wall
  • a BSW 11 is formed around the PCV 12.
  • the BSW 11 that needs to be disposed as radioactive waste is referred to as a BSW activation unit 11a.
  • FIG. 15 is a flowchart of a general dismantling method for the reactor containment vessel and the biological shielding wall in the reactor building.
  • FIG. 15 shows a nuclear reactor disassembly procedure that is assumed when the BSW non-activation part is not dismantled before the management zone is released.
  • Step 1 After the in-furnace structure 15 of the RPV 14 is removed, the RPV 14, RSW 16 and the like are dismantled and removed.
  • Step 2 A work scaffold is installed inside the PCV 12 from which the RPV 14 and RSW 16 have been removed and dismantled.
  • Step 3 A work scaffold is installed inside the BSW 11 from which the PCV 12 has been removed, and the BSW activation unit 11a is dismantled and removed.
  • Step 4 After the demolition and removal of all radioactive waste is completed, the controlled area will be released.
  • Step 5 The building concrete such as the BSW non-activation part 11b below the clearance level is dismantled and removed.
  • the BSW non-activation part 11b may be disassembled after the management area is released, but generally only the BSW activation part 11a is removed before the management area is released.
  • the gap between the BSW 11 and the PCV 12 is only about several tens of millimeters and there is no work space.
  • the PCV 12 in order to disassemble the BSW activation unit 11a, the PCV 12 must be dismantled in advance.
  • the reactor demolition apparatus disclosed in Patent Document 1 has an elevator lift and a cutting scaffold installed inside the BSW, and a cutting apparatus and a recovery apparatus are movably attached to the BSW to automate the cutting and demolition work of the BSW. Yes.
  • an object of the present invention is to provide a reactor containment vessel and a biological shielding wall dismantling method that can avoid work at a high place and improve work safety.
  • the present invention includes a BSW dismantling step of dismantling the biological shielding wall from each floor side of the reactor building, A PCV dismantling step of dismantling the reactor containment vessel from the floor side dismantling the biological shielding wall; It is another object of the present invention to provide a method for dismantling a reactor containment vessel and a biological shielding wall. According to the first means, during the demolition work of the reactor containment vessel and the biological shielding wall of the reactor building after decommissioning, an accident, etc., the work at a high place from the inside of the reactor containment vessel is avoided, and the dismantling is performed. Work safety can be increased.
  • the present invention provides a BSW dismantling process in which a biological shielding wall is disassembled from each floor side of a reactor building in which a reactor internal structure, a reactor pressure vessel, and a heat shielding wall are disassembled.
  • a PCV dismantling step of dismantling the reactor containment vessel from the floor side dismantling the biological shielding wall It is another object of the present invention to provide a method for dismantling a reactor containment vessel and a biological shielding wall.
  • the second means when the reactor containment vessel and the biological shielding wall are disassembled, it is possible to avoid work at a high place from the inside of the reactor containment vessel and to improve the safety of the disassembly operation.
  • the present invention provides the first or second means, wherein each floor is reinforced with a temporary reinforcing member before the biological shielding wall is disassembled.
  • An object of the present invention is to provide a method for dismantling the reactor containment vessel and the biological shielding wall. According to the third means, it is possible to prevent damage due to insufficient strength of the floor at the time of BSW dismantling and to ensure work safety.
  • the present invention closes the upper surface opening of the reactor containment vessel with a lid before the BSW dismantling process. It is another object of the present invention to provide a reactor containment vessel and a biological shielding wall dismantling method. According to the fourth means, in the BSW dismantling work on the upper floor than the upper surface opening of the PCV, the glass (concrete fragments) generated during the work prevents falling into the PCV and diffusion of radioactive material. Thus, the safety of the dismantling work can be ensured.
  • the BSW dismantling step includes disposing the BSW non-activation part and then disposing the BSW activation part.
  • An object of the present invention is to provide a method for dismantling a reactor containment vessel and a biological shielding wall, characterized by disassembling and replacing the dismantling apparatus before dismantling work of the BSW activation section. According to the fifth means, it is possible to prevent the dismantled product of the BSW activation part having a high radioactivity concentration from being mixed into the dismantled product of the BSW non-activation part below the clearance level, and the amount of waste having a high radioactivity concentration. Can be reduced.
  • the PCV dismantling step is configured such that the PCV cylindrical portion is placed on each floor in order from the upper floor.
  • An object of the present invention is to provide a reactor containment vessel and a method for dismantling a biological shielding wall, which are cut into a ring shape, and then carried out to an operating floor and subdivided. According to the sixth means, it is possible to efficiently subdivide the PCV cylindrical portion on the operating floor having a work space. Also, work at heights can be avoided.
  • the present invention provides the reactor containment vessel and the biological shielding according to the sixth means, wherein the PCV cylindrical portion is slung with an overhead crane before cutting work.
  • the purpose is to provide a wall demolition method.
  • the safety of the work can be ensured by preventing the PCV cylindrical portion from falling after being cut.
  • the PCV dismantling step is performed after the PCV spherical portion is segmented on each floor and then operated.
  • An object of the present invention is to provide a reactor containment vessel and a biological shielding wall dismantling method characterized in that the reactor containment vessel is carried out to the floor and subdivided. According to the eighth means, it is possible to efficiently subdivide the PCV spherical portion on an operating floor having a work space.
  • the PCV spherical portion is slung with a small crane before the cutting operation, and the reactor containment vessel and the biological shield The purpose is to provide a wall demolition method. According to the ninth means, it is possible to prevent the PCV spherical portion from falling after being cut and to ensure work safety.
  • FIG. 1 is a flow diagram of a method for dismantling a reactor containment vessel and a biological shielding wall according to the present invention.
  • FIG. 2 is a detailed flowchart of BSW disassembly.
  • FIG. 3 is a detailed flowchart of PCV disassembly.
  • the reactor containment vessel and biological shielding wall dismantling method of the present invention is applied to decommissioning (stopping the reactor and dismantling the reactor and related equipment), and after the accident (such as natural disasters or inability to control operation). Applicable to the furnace building.
  • Step 10 After removing the internal structure 15 of the RPV 14 having a relatively high dose, the RPV 14, RSW 16 and the like are dismantled and removed.
  • Step 20 In the reactor containment vessel and biological shielding wall dismantling method of the present invention, the BSW 11 is disassembled from each floor of the reactor building 10 toward the inside from the outside of the reactor storage unit. For this reason, after first disassembling the BSW non-activation part 11b below the clearance level, the BSW activation part 11a is dismantled. It is assumed that the boundary between the BSW activation unit 11a and the BSW non-activation unit 11b is known by prior measurement / evaluation of the radiation dose.
  • FIGS. 4A and 4B are explanatory views showing preparation work for BSW disassembly.
  • FIG. 4A is a side cross-sectional view
  • FIG. 4B is a cross-sectional view along line AA in FIG.
  • first, temporary reinforcing members 18 are installed on each floor in order to secure the building strength after the dismantling of the BSW 11.
  • the installation location and required strength of the temporary reinforcing member 18 are set in advance by analysis of the reactor building 10 or the like.
  • the temporary reinforcing member 18 is basically a square support, and is attached between the ceiling and the floor from which the wall is removed (the end of the wall surface) to maintain structural strength instead of the wall.
  • the temporary reinforcing member 18 is connected to a rectangular shape (such as a quadrangle) according to the shape of the wall to be removed, or a cube or a rectangular parallelepiped frame having a rectangular frame as a part thereof. It may be adopted.
  • a frame by providing a ceiling, it can function as a shelter even if the floor collapses during an operation.
  • Step 202 A lid 22 that closes the PCV upper opening is installed using the overhead crane 20 of the operating floor 40 of the reactor building 10. Since the top floor (F1) of the floor where the BSW 11 is dismantled does not have the wall surface of the PCV 12 inside, it is possible to prevent the concrete glass from falling into the PCV 12 when the wall is removed by installing the lid 22, and of the radioactive material Diffusion can be prevented.
  • Step 203 The wall which interferes with carrying in of the demolition apparatus to the demolition place (each floor) of the reactor building 10 is removed. This work is performed as necessary.
  • FIG. 5 is an explanatory view of the dismantling work of the BSW non-activation part 11b of the top floor (F1) among the dismantling target floors.
  • the dismantling device 24 is carried into the site.
  • the dismantling device 24 shown is a small heavy machine equipped with a breaker. Note that the adopted construction method is not limited to this as long as the BSW non-activation part 11b and the BSW activation part 11a can be disassembled separately, and for example, a concrete cutter, a wire saw, or the like can be applied. Further, the dismantling device 24 is not necessarily remote-controlled.
  • Step 205 In the dismantling place, an appropriate curing 26 using a sheet or the like and a local exhaust facility 28 are provided. As a result, it is possible to prevent non-radioactive dust generated by crushing concrete and contamination due to radioactive dust from diffusing into the building.
  • FIG. 6 is an explanatory view of the work of collecting the dismantled concrete glass.
  • the generated glass is collected by a heavy machine 30 with an excavator for collecting glass and placed on a glass transport carriage 32.
  • a heavy machine it is not necessary to use a heavy machine in particular, and it is also possible to collect the glass manually and load it on the glass transport carriage 32.
  • the glass loaded on the glass transport carriage 32 is transferred to a storage location (not shown).
  • the storage location is other floor in the reactor building 10 or other than the reactor building 10
  • the glass carriage 32 is moved to the operating floor 40 and an opening (not shown) communicating with each floor.
  • the crane is suspended to a predetermined place by the overhead crane 20.
  • FIG. 7 is an explanatory diagram after partial disassembly of the BSW non-activation part of the top floor (F1).
  • the dismantling device 24 and the glass transport cart 32 used in the dismantling of the BSW non-activation unit 11b are replaced with the dismantling device 24 and the glass transport cart 32 for dismantling the BSW activation unit 11a. Thereby, the contamination between the BSW non-activation part 11b and the BSW activation part 11a can be prevented.
  • Step 209 Thereafter, all the concrete in the region on the reactor side (BSW activation portion 11a) is dismantled from the range disassembled in FIG.
  • the demolished concrete is carried out to an external storage place by the glass transport cart 32 as in FIG. At this time, it is desirable to measure the radioactivity of the glass with a survey meter or the like in parallel.
  • FIG. 8 is an explanatory diagram of preparation for dismantling the BSW on the lower floor.
  • the BSW dismantling of the upper floor is completed, it is cleaned and cleaned, and the dismantling device 24 and the like are moved down by the overhead crane 20 and moved.
  • the lid 22 is removed with the overhead crane 20.
  • FIG. 9 is an explanatory diagram of the BSW dismantling of the lower floor.
  • FIG. 10 is an explanatory diagram of the reactor building after all BSW activation parts and BSW non-activation parts have been removed. As shown, the concrete wall (BSW) around the reactor has been removed. For this reason, it can be accessed from the outside of the PCV 12. In the dismantling procedure described so far, the BSW non-activation part 11b and the BSW activation part 11a of a certain floor are successively disassembled, and then the operation moves to the lower floor work. As another procedure, the disassembly of the BSW activation unit 11a may be started after the removal of the BSW non-activation unit 11b on each floor is completed.
  • FIG. 11 is an explanatory view of the PCV cylindrical part disassembly.
  • the PCV disassembly of this embodiment employs manual gas cutting as an example and will be described below. Therefore, first, a contamination diffusion prevention / fire curing 34 is applied to the floor where the cutting operation is performed and above the floor.
  • the cutting method is not limited to gas cutting, but may be mechanical cutting using a disk cutter or the like. Moreover, when considering reduction of exposure, the cutting work may be remoted.
  • Step 302 Next, the work scaffold 36 is assembled and installed on the floor on which the work is performed in order to approach the PCV cylindrical portion for cutting. [Step 303] Further, a dismantling device 24 for finely cutting the PCV cut piece is carried in. [Step 304]
  • the lifting balance 38 has a structure in which a plurality of points can be hung in the circumferential direction of the PCV cylindrical portion 12a. The staking work may be performed by the worker approaching the PCV 12 from the work scaffold 36.
  • the lifting balance 38 and the PCV 12 may be connected by attaching a temporary lifting point (not shown) to the PCV 12 by welding or the like, and connecting the lifting balance 38 and the PCV 12 with a wire rope or a chain block.
  • Step 305 After the PCV 12 is slung on the lifting balance 38, the operator cuts the gas while moving in the circumferential direction of the PCV 12 on the work scaffold 36, thereby dividing the PCV 12 into a ring shape.
  • Step 306 The ring-shaped cut pieces are lifted on the operating floor 40 by the overhead crane 20 and are roughly cut by gas cutting into four or six divisions in the vertical direction (axial direction of the cylinder) by hand. Furthermore, it is shredded by a dismantling device 24 such as a band saw into a size that fits into the waste container 41. The waste container 41 storing the waste is transferred to a temporary storage place for a container (not shown).
  • Step 307 When the ring-shaped cutting operation of the PCV 12 on the work floor is completed, it is cleaned and cleaned and moved to the lower floor.
  • the above-described dismantling work of the PCV cylindrical portion 12a is repeated on each floor, and the disassembling of the PCV cylindrical portion 12a is completed. Thereafter, the process proceeds to the dismantling work of the PCV spherical portion 12b.
  • FIG. 12 is an explanatory view 1 of the dismantling work of the PCV spherical portion.
  • FIG. 13 is an explanatory diagram 2 of the dismantling work of the PCV spherical portion.
  • FIG. 14 is an explanatory diagram 3 of the dismantling work of the PCV spherical portion.
  • the cutting work is performed by accessing the vicinity of the PCV 12 with the high work platform 42. Further, since it is difficult to suspend the PCV spherical portion 12b being cut by the overhead crane 20, the cutting work is performed while being suspended by the small crane 44 disposed on the upper floor.
  • Step 308 First, the high work platform 42 and the small crane 44 are transferred to each work floor. Thereafter, the PCV spherical portion 12 b is hung on the small crane 44.
  • the PCV spherical portion 12b cannot be raised to the operating floor 40 as it is because of the dimensional shape. For this reason, the PCV spherical portion 12b is cut into a fine panel shape to some extent.
  • the high work platform 42 is brought close to the cut portion of the PCV spherical portion 12b, and a hanging point (not shown) is welded to the cut portion, for example, and this is hung on the small crane 44.
  • Step 310 After the staking is completed, the PCV spherical portion 12b is cut from the high work platform 42.
  • the cutting method applies gas cutting in the same manner as the PCV cylindrical portion 12a. Therefore, a contamination diffusion prevention / fire curing 34 is applied to the floor where the cutting operation is performed and above.
  • the cutting method is not limited to gas cutting, but may be mechanical cutting using a disk cutter or the like. Moreover, when considering reduction of exposure, the cutting work may be remoted.
  • Step 311 After cutting, the cut piece is once suspended by the small crane 44 on the bottom of the PCV 12.
  • Step 312 Next, an operator removes a cut piece from the small crane 44 to the bottom of the PCV 12, hangs it on the overhead crane 20, and moves to the operating floor 40.
  • Step 313 Thereafter, the cut pieces are shredded and stored in the waste storage container 41 on the operating floor 40, and the waste storage container 41 is moved to the storage location.
  • Step 314 When the work on the work floor is completed, cleaning and cleaning are performed, the small crane 44 is moved to the lower floor (see FIGS. 13 and 14), and the next dismantling work is performed. Steps 308 to 314 are repeated to complete the disassembly work of the PCV spherical portion 12b.
  • Step 40 After all radioactive waste is removed, the controlled area will be released.
  • Step 50 The building concrete of the remaining reactor building 10 is dismantled.
  • the reactor containment vessel and the biological shielding wall dismantling method of the present invention it is possible to increase the safety of dismantling / removing work of PCV and BSW because there is no work at high places.
  • the preferred embodiments of the present invention have been described above. However, the present invention is not limited to the above embodiment, and various modifications can be made without departing from the spirit of the present invention. Moreover, the present invention is not limited to the combinations shown in the embodiments, and can be implemented by various combinations. For example, it is not essential to apply only to the reactor building in which the reactor internal structure, the reactor pressure vessel, and the heat shield wall are disassembled, and the BSW and PCV may be dismantled from the floor side.
  • the present invention has industrial applicability in the nuclear industry field where the decommissioning work of a nuclear power plant that has passed its useful life has been carried out.

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  • General Engineering & Computer Science (AREA)
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Abstract

This method for dismantling a nuclear reactor containment vessel and a biological shielding wall avoids work at height and has improved work safety. In the present invention, said method is characterised by comprising: a BSW dismantling step in which the biological shielding wall (11) is dismantled from each floor side of a nuclear reactor building (10) from which a reactor-internal structure (15), a nuclear reactor pressure vessel (14) and a thermal shielding wall (16) have been dismantled; and a PCV dismantling step in which the nuclear reactor containment vessel (12) is dismantled from each floor side from which the biological shielding wall (11) has been dismantled.

Description

原子炉格納容器及び生体遮蔽壁の解体工法Dismantling method of reactor containment vessel and biological shielding wall
　本発明は、原子炉格納容器（以下、単にＰＣＶ（Ｐｒｉｍａｒｙ　Ｃｏｎｔａｉｎｍｅｎｔ　Ｖｅｓｓｅｌ）ということあり）及び生体遮蔽壁（以下、単にＢＳＷ（Ｂｉｏｌｏｇｉｃａｌ　Ｓｈｉｅｌｄ　Ｗａｌｌ）ということあり）の解体工法に関する。 The present invention relates to a dismantling method for a nuclear reactor containment vessel (hereinafter sometimes simply referred to as PCV (Primary Continent Vessel)) and a biological shielding wall (hereinafter simply referred to as BSW (Biological Shield Wall)).
　図１６は原子炉建屋の主要部の一例を示した断面図である。原子炉建屋１０内にはＰＣＶ１２が形成され、このＰＣＶ１２内に原子炉圧力容器（以下、単にＲＰＶ（Ｒｅａｃｔｏｒ　Ｐｒｅｓｓｕｒｅ　Ｖｅｓｓｅｌ）ということあり）１４が据え付けられている。ＲＰＶ１４の内部には炉内構造物１５が取り付けられている。またＲＰＶ１４の周囲には熱遮蔽壁（以下、単にＲＳＷ（Ｒｅａｃｔｏｒ　Ｓｈｉｅｌｄ　Ｗａｌｌ）ということあり）１６が設けられている。ＰＣＶ１２の周囲にはＢＳＷ１１が形成されている。
　このＢＳＷ１１のＰＣＶ１２側は、原子炉運転中に発生する中性子の影響で放射化するため、解体撤去する際にＰＣＶ１２側表面から一定深さの範囲は放射性廃棄物として処分する必要がある。ここで本発明では、以下、放射性廃棄物として処分が必要なＢＳＷ１１をＢＳＷ放射化部１１ａという。 FIG. 16 is a cross-sectional view showing an example of a main part of the reactor building. A PCV 12 is formed in the reactor building 10, and a reactor pressure vessel (hereinafter simply referred to as RPV (Reactor Pressure Vessel)) 14 is installed in the PCV 12. An in-furnace structure 15 is attached inside the RPV 14. Further, around the RPV 14, a heat shielding wall (hereinafter sometimes simply referred to as “RSW (Reactor Shield Wall)”) 16 is provided. A BSW 11 is formed around the PCV 12.
Since the PCV12 side of this BSW11 is activated by the influence of neutrons generated during the operation of the reactor, it is necessary to dispose of a certain depth range from the PCV12 side surface as radioactive waste when dismantling and removal. Here, in the present invention, hereinafter, the BSW 11 that needs to be disposed as radioactive waste is referred to as a BSW activation unit 11a.
　一方、それより外側の範囲は、クリアランスレベル（放射性廃棄物として扱う必要のない放射性濃度レベル）以下となるため、解体撤去の際、管理区域（法令で定めた放射線レベルを超える可能性のある区域）解除後に原子炉建屋１０本体と一緒に解体し廃棄処分等することも可能である。ここで本発明では、このＢＳＷ放射化部１１ａより外側の放射性廃棄物として処分する必要がないＢＳＷ１１をＢＳＷ非放射化部１１ｂという。
　耐久年数の経過した原子炉建屋１０は所定の廃止措置がとられる。図１５は原子炉建屋内の原子炉格納容器及び生体遮蔽壁の一般的な解体工法のフロー図である。なお図１５は、管理区域解除前にＢＳＷ非放射化部を解体しない場合に想定される原子炉解体手順を示している。 On the other hand, since the area outside it is below the clearance level (radioactive concentration level that does not need to be treated as radioactive waste), the controlled area (area that may exceed the radiation level stipulated by laws and regulations) ) After the release, it can be dismantled and disposed of together with the reactor building 10 main body. Here, in the present invention, the BSW 11 that does not need to be disposed as radioactive waste outside the BSW activation unit 11a is referred to as a BSW non-activation unit 11b.
A predetermined decommissioning measure is taken for the reactor building 10 whose durability has passed. FIG. 15 is a flowchart of a general dismantling method for the reactor containment vessel and the biological shielding wall in the reactor building. FIG. 15 shows a nuclear reactor disassembly procedure that is assumed when the BSW non-activation part is not dismantled before the management zone is released.
［ステップ１］
　ＲＰＶ１４の炉内構造物１５を撤去した後、ＲＰＶ１４、ＲＳＷ１６等を解体撤去する。
［ステップ２］
　ＲＰＶ１４及びＲＳＷ１６が撤去されたＰＣＶ１２の内部に作業足場を設置して解体撤去する。
［ステップ３］
　ＰＣＶ１２が撤去されたＢＳＷ１１の内部に作業足場を設置してＢＳＷ放射化部１１ａを解体撤去する。
［ステップ４］
　すべての放射性廃棄物の解体撤去が完了した後、管理区域を解除する。
［ステップ５］
　クリアランスレベル以下のＢＳＷ非放射化部１１ｂなど建物コンクリートを解体撤去する。 [Step 1]
After the in-furnace structure 15 of the RPV 14 is removed, the RPV 14, RSW 16 and the like are dismantled and removed.
[Step 2]
A work scaffold is installed inside the PCV 12 from which the RPV 14 and RSW 16 have been removed and dismantled.
[Step 3]
A work scaffold is installed inside the BSW 11 from which the PCV 12 has been removed, and the BSW activation unit 11a is dismantled and removed.
[Step 4]
After the demolition and removal of all radioactive waste is completed, the controlled area will be released.
[Step 5]
The building concrete such as the BSW non-activation part 11b below the clearance level is dismantled and removed.
　このようにＢＳＷ非放射化部１１ｂは、管理区域解除後に解体すればよいが、管理区域解除前は一般的にはＢＳＷ放射化部１１ａのみを除去することになる。このとき、ＢＳＷ１１とＰＣＶ１２の隙間はわずか数十ミリ程度であり作業スペースがない。このためＢＳＷ放射化部１１ａを解体するには、あらかじめＰＣＶ１２を解体撤去しなければならない。特許文献１に開示の原子炉解体装置は、ＢＳＷの内部にエレベータリフトと切断用足場を設置して、これに切断装置と回収装置を移動自在に装着してＢＳＷの切断解体作業を自動化している。 As described above, the BSW non-activation part 11b may be disassembled after the management area is released, but generally only the BSW activation part 11a is removed before the management area is released. At this time, the gap between the BSW 11 and the PCV 12 is only about several tens of millimeters and there is no work space. For this reason, in order to disassemble the BSW activation unit 11a, the PCV 12 must be dismantled in advance. The reactor demolition apparatus disclosed in Patent Document 1 has an elevator lift and a cutting scaffold installed inside the BSW, and a cutting apparatus and a recovery apparatus are movably attached to the BSW to automate the cutting and demolition work of the BSW. Yes.
特許第４０８７５０９号公報Japanese Patent No. 4087509
　ＰＣＶを解体した後にＢＳＷ放射化部を解体する手順をとる場合、解体箇所へのアクセスは、いずれも内側（原子炉格納容器側）からとなる。このときＰＣＶ又はＢＳＷは内部の炉内構造物、ＲＰＶ、ＲＳＷが解体撤去された状態である。解体作業は炉底部から最高数十メートル程度の高所となるため、十分な安全性が確保できるように努めなければならない。
　特許文献１についても、装置を設置する際には足場を用いた高所作業が必要となり、同様のリスクが伴っている。 When taking the procedure of disassembling the BSW activation part after disassembling the PCV, access to the dismantling part is from the inside (reactor containment vessel side). At this time, PCV or BSW is in a state in which the internal furnace structure, RPV, RSW is dismantled and removed. Since the demolition work is at a height of up to several tens of meters from the bottom of the furnace, efforts must be made to ensure sufficient safety.
Also in Patent Document 1, when the apparatus is installed, a work at a high place using a scaffold is required, which is accompanied by a similar risk.
　そこで上記従来技術の問題点に鑑み本発明は、高所作業を回避して作業の安全性を高めた原子炉格納容器及び生体遮蔽壁の解体工法を提供することを目的としている。 Therefore, in view of the above-mentioned problems of the prior art, an object of the present invention is to provide a reactor containment vessel and a biological shielding wall dismantling method that can avoid work at a high place and improve work safety.
　上記課題を解決するための第１の手段として、本発明は、原子炉建屋の各フロア側から生体遮蔽壁を解体するＢＳＷ解体工程と、
　前記生体遮蔽壁を解体したフロア側から原子炉格納容器を解体するＰＣＶ解体工程と、
　を有することを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第１の手段によれば、廃炉、事故後などの原子炉建屋の原子炉格納容器及び生体遮蔽壁の解体作業時において、原子炉格納容器内側からの高所作業を回避して、解体作業の安全性を高めることができる。 As a first means for solving the above problems, the present invention includes a BSW dismantling step of dismantling the biological shielding wall from each floor side of the reactor building,
A PCV dismantling step of dismantling the reactor containment vessel from the floor side dismantling the biological shielding wall;
It is another object of the present invention to provide a method for dismantling a reactor containment vessel and a biological shielding wall.
According to the first means, during the demolition work of the reactor containment vessel and the biological shielding wall of the reactor building after decommissioning, an accident, etc., the work at a high place from the inside of the reactor containment vessel is avoided, and the dismantling is performed. Work safety can be increased.
　上記課題を解決するための第２の手段として、本発明は、炉内構造物と原子炉圧力容器と熱遮蔽壁を解体した原子炉建屋の各フロア側から生体遮蔽壁を解体するＢＳＷ解体工程と、
　前記生体遮蔽壁を解体したフロア側から原子炉格納容器を解体するＰＣＶ解体工程と、
　を有することを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第２の手段によれば、原子炉格納容器及び生体遮蔽壁の解体作業時において、原子炉格納容器内側からの高所作業を回避して、解体作業の安全性を高めることができる。 As a second means for solving the above problems, the present invention provides a BSW dismantling process in which a biological shielding wall is disassembled from each floor side of a reactor building in which a reactor internal structure, a reactor pressure vessel, and a heat shielding wall are disassembled. When,
A PCV dismantling step of dismantling the reactor containment vessel from the floor side dismantling the biological shielding wall;
It is another object of the present invention to provide a method for dismantling a reactor containment vessel and a biological shielding wall.
According to the second means, when the reactor containment vessel and the biological shielding wall are disassembled, it is possible to avoid work at a high place from the inside of the reactor containment vessel and to improve the safety of the disassembly operation.
　上記課題を解決するための第３の手段として、本発明は、第１又は第２の手段において、前記生体遮蔽壁を解体する前に各フロアを仮設補強部材で補強することを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第３の手段によれば、ＢＳＷ解体時においてフロアの強度不足による破損を防止して、作業の安全性を確保できる。 As a third means for solving the above-mentioned problem, the present invention provides the first or second means, wherein each floor is reinforced with a temporary reinforcing member before the biological shielding wall is disassembled. An object of the present invention is to provide a method for dismantling the reactor containment vessel and the biological shielding wall.
According to the third means, it is possible to prevent damage due to insufficient strength of the floor at the time of BSW dismantling and to ensure work safety.
　上記課題を解決するための第４の手段として、本発明は、第１ないし第３のいずれか１の手段において、前記ＢＳＷ解体工程の前に前記原子炉格納容器の上面開口を蓋で塞ぐことを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第４の手段によれば、ＰＣＶの上面開口よりも上階フロアのＢＳＷ解体作業において、作業中に発生するガラ（コンクリート破砕片）等がＰＣＶ内部への落下及び放射性物質の拡散を防止して、解体作業の安全性を確保できる。 As a fourth means for solving the above-mentioned problem, in the first to third means, the present invention closes the upper surface opening of the reactor containment vessel with a lid before the BSW dismantling process. It is another object of the present invention to provide a reactor containment vessel and a biological shielding wall dismantling method.
According to the fourth means, in the BSW dismantling work on the upper floor than the upper surface opening of the PCV, the glass (concrete fragments) generated during the work prevents falling into the PCV and diffusion of radioactive material. Thus, the safety of the dismantling work can be ensured.
　上記課題を解決するための第５の手段として、本発明は、第１ないし第４のいずれか１の手段において、前記ＢＳＷ解体工程は、ＢＳＷ非放射化部を解体した後にＢＳＷ放射化部を解体し、前記ＢＳＷ放射化部の解体作業前に解体装置を換えることを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第５の手段によれば、クリアランスレベル以下のＢＳＷ非放射化部の解体物に放射能濃度の高いＢＳＷ放射化部の解体物が混入することを防止して、放射能濃度の高い廃棄物量を低減できる。 As a fifth means for solving the above-mentioned problem, in the present invention, in any one of the first to fourth means, the BSW dismantling step includes disposing the BSW non-activation part and then disposing the BSW activation part. An object of the present invention is to provide a method for dismantling a reactor containment vessel and a biological shielding wall, characterized by disassembling and replacing the dismantling apparatus before dismantling work of the BSW activation section.
According to the fifth means, it is possible to prevent the dismantled product of the BSW activation part having a high radioactivity concentration from being mixed into the dismantled product of the BSW non-activation part below the clearance level, and the amount of waste having a high radioactivity concentration. Can be reduced.
　上記課題を解決するための第６の手段として、本発明は、第１ないし第５のいずれか１の手段において、前記ＰＣＶ解体工程は、ＰＣＶ円筒部を上階のフロアから順番に各フロアでリング状に切断した後、オペレイティングフロアへ搬出して細分化することを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第６の手段によれば、作業スペースのあるオペレイティングフロアで効率良くＰＣＶ円筒部を細分化処理することができる。また高所作業を回避できる。 As a sixth means for solving the above-mentioned problems, in the present invention, in any one of the first to fifth means, the PCV dismantling step is configured such that the PCV cylindrical portion is placed on each floor in order from the upper floor. An object of the present invention is to provide a reactor containment vessel and a method for dismantling a biological shielding wall, which are cut into a ring shape, and then carried out to an operating floor and subdivided.
According to the sixth means, it is possible to efficiently subdivide the PCV cylindrical portion on the operating floor having a work space. Also, work at heights can be avoided.
　上記課題を解決するための第７の手段として、本発明は、第６の手段において、前記ＰＣＶ円筒部は、切断作業前に天井クレーンで玉掛けすることを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第７の手段によれば、ＰＣＶ円筒部の切断後の落下を防止して作業の安全性を確保できる。 As a seventh means for solving the above-mentioned problems, the present invention provides the reactor containment vessel and the biological shielding according to the sixth means, wherein the PCV cylindrical portion is slung with an overhead crane before cutting work. The purpose is to provide a wall demolition method.
According to the seventh means, the safety of the work can be ensured by preventing the PCV cylindrical portion from falling after being cut.
　上記課題を解決するための第８の手段として、本発明は、第１ないし第７のいずれか１の手段において、前記ＰＣＶ解体工程は、ＰＣＶ球形部を各フロアで小片化した後、オペレイティングフロアへ搬出して細分化することを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第８の手段によれば、作業スペースのあるオペレイティングフロアで効率良くＰＣＶ球形部を細分化処理することができる。
　上記課題を解決するための第９の手段として、本発明は、第８の手段において、前記ＰＣＶ球形部は、切断作業前に小型クレーンで玉掛けすることを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法を提供することにある。
　上記第９の手段によれば、ＰＣＶ球形部の切断後の落下を防止して作業の安全性を確保できる。 As an eighth means for solving the above-mentioned problems, in the present invention, in any one of the first to seventh means, the PCV dismantling step is performed after the PCV spherical portion is segmented on each floor and then operated. An object of the present invention is to provide a reactor containment vessel and a biological shielding wall dismantling method characterized in that the reactor containment vessel is carried out to the floor and subdivided.
According to the eighth means, it is possible to efficiently subdivide the PCV spherical portion on an operating floor having a work space.
As a ninth means for solving the above-mentioned problem, in the eighth means according to the present invention, the PCV spherical portion is slung with a small crane before the cutting operation, and the reactor containment vessel and the biological shield The purpose is to provide a wall demolition method.
According to the ninth means, it is possible to prevent the PCV spherical portion from falling after being cut and to ensure work safety.
　本発明によれば、高所作業がなくなりＰＣＶ及びＢＳＷの解体撤去作業の安全性を高めることができる。 According to the present invention, work at high places is eliminated, and the safety of dismantling and removal work of PCV and BSW can be improved.
本発明の原子炉格納容器及び生体遮蔽壁の解体工法のフロー図である。It is a flowchart of the dismantling method of the nuclear reactor containment vessel and biological shielding wall of this invention. ＢＳＷ解体の詳細フロー図である。It is a detailed flowchart of BSW dismantling. ＰＣＶ解体の詳細フロー図である。It is a detailed flowchart of PCV dismantling. ＢＳＷ解体の準備作業を示す説明図である。It is explanatory drawing which shows the preparatory work of BSW dismantling. 解体対象フロアのうち最上階フロア（Ｆ１）のＢＳＷ非放射化部の解体作業  の説明図である。It is explanatory drawing of the dismantling work basket of the BSW non-radiation part of the top floor (F1) among dismantling object floors. 解体したコンクリートガラの回収作業の説明図である。It is explanatory drawing of the collection | recovery operation | work of the disassembled concrete glass. 最上階フロア（Ｆ１）のＢＳＷ非放射化部の一部解体後の説明図である。It is explanatory drawing after a partial disassembly of the BSW non-activation part of the top floor (F1). 下階フロアのＢＳＷ解体準備の説明図である。It is explanatory drawing of BSW dismantling preparation of a lower floor. 下階フロアのＢＳＷ解体の説明図である。It is explanatory drawing of BSW dismantling of a lower floor. 全てのＢＳＷ放射化部およびＢＳＷ非放射化部撤去後の原子炉建屋の説明図である。It is explanatory drawing of the reactor building after all the BSW activation parts and BSW non-activation part removal. ＰＣＶ円筒部解体の説明図である。It is explanatory drawing of a PCV cylindrical part disassembly. ＰＣＶ球形部の解体作業の説明図１である。It is explanatory drawing 1 of the dismantling operation | work of a PCV spherical part. ＰＣＶ球形部の解体作業の説明図２である。It is explanatory drawing 2 of the dismantling operation | work of a PCV spherical part. ＰＣＶ球形部の解体作業の説明図３である。It is explanatory drawing 3 of the dismantling operation | work of a PCV spherical part. 原子炉建屋内の原子炉格納容器及び生体遮蔽壁の一般的な解体工法のフロー図である。It is a flowchart of the general demolition construction method of the reactor containment vessel and biological shielding wall in a reactor building. 原子炉建屋の主要部の一例を示した断面図である。It is sectional drawing which showed an example of the principal part of a reactor building.
　本発明の原子炉格納容器及び生体遮蔽壁の解体工法の実施形態について、図面を参照しながら、以下詳細に説明する。
　図１は、本発明の原子炉格納容器及び生体遮蔽壁の解体工法のフロー図である。図２はＢＳＷ解体の詳細フロー図である。図３はＰＣＶ解体の詳細フロー図である。本発明の原子炉格納容器及び生体遮蔽壁の解体工法は、廃炉（原子炉を停止させて原子炉及び関連する設備を解体すること）、事故後（自然災害又は運転制御不能など）の原子炉建屋を適用対象としている。 Embodiments of the reactor containment vessel and the biological shielding wall dismantling method of the present invention will be described below in detail with reference to the drawings.
FIG. 1 is a flow diagram of a method for dismantling a reactor containment vessel and a biological shielding wall according to the present invention. FIG. 2 is a detailed flowchart of BSW disassembly. FIG. 3 is a detailed flowchart of PCV disassembly. The reactor containment vessel and biological shielding wall dismantling method of the present invention is applied to decommissioning (stopping the reactor and dismantling the reactor and related equipment), and after the accident (such as natural disasters or inability to control operation). Applicable to the furnace building.
［ステップ１０］
　比較的高線量なＲＰＶ１４の炉内構造物１５を撤去した後、ＲＰＶ１４、ＲＳＷ１６等を解体撤去する。
［ステップ２０］
　本発明の原子炉格納容器及び生体遮蔽壁の解体工法では、原子炉建屋１０の各フロアからＢＳＷ１１を原子炉収納部の外側から内側に向かって解体して行く。このため、まずクリアランスレベル以下のＢＳＷ非放射化部１１ｂを解体した後、ＢＳＷ放射化部１１ａを解体する。なおＢＳＷ放射化部１１ａとＢＳＷ非放射化部１１ｂの境界は、事前の放射線量の測定・評価等によって既知であるとする。 [Step 10]
After removing the internal structure 15 of the RPV 14 having a relatively high dose, the RPV 14, RSW 16 and the like are dismantled and removed.
[Step 20]
In the reactor containment vessel and biological shielding wall dismantling method of the present invention, the BSW 11 is disassembled from each floor of the reactor building 10 toward the inside from the outside of the reactor storage unit. For this reason, after first disassembling the BSW non-activation part 11b below the clearance level, the BSW activation part 11a is dismantled. It is assumed that the boundary between the BSW activation unit 11a and the BSW non-activation unit 11b is known by prior measurement / evaluation of the radiation dose.
［ステップ２０１］
　図４はＢＳＷ解体の準備作業を示す説明図であり（１）は側面断面図、（２）は（１）のＡ－Ａ断面図である。ＢＳＷ非放射化部１１ｂを含むＢＳＷ１１を解体する前に、まずＢＳＷ１１解体後の建物強度を担保するために仮設補強部材１８を各フロアに設置する。なお仮設補強部材１８の設置箇所および必要強度等については、あらかじめ原子炉建屋１０の解析等で設定しておく。
　仮設補強部材１８は、基本的に四角支柱であり、壁を撤去する天井及び床の間に取り付けて（壁面の端部）、壁の換わりに構造的な強度を保持している。その他の構成として仮設補強部材１８は、撤去する壁の形状に合わせた矩形状（四角形など）に連結したり、矩形状の枠をその一部とする立方体や直方体の枠体としたりする構成を採用しても良い。枠体の場合、天井を設けることにより、万が一作業中にフロアが倒壊してもシェルターとして機能させることができる。 [Step 201]
FIGS. 4A and 4B are explanatory views showing preparation work for BSW disassembly. FIG. 4A is a side cross-sectional view, and FIG. 4B is a cross-sectional view along line AA in FIG. Before disassembling the BSW 11 including the BSW non-activation part 11b, first, temporary reinforcing members 18 are installed on each floor in order to secure the building strength after the dismantling of the BSW 11. The installation location and required strength of the temporary reinforcing member 18 are set in advance by analysis of the reactor building 10 or the like.
The temporary reinforcing member 18 is basically a square support, and is attached between the ceiling and the floor from which the wall is removed (the end of the wall surface) to maintain structural strength instead of the wall. As other configurations, the temporary reinforcing member 18 is connected to a rectangular shape (such as a quadrangle) according to the shape of the wall to be removed, or a cube or a rectangular parallelepiped frame having a rectangular frame as a part thereof. It may be adopted. In the case of a frame, by providing a ceiling, it can function as a shelter even if the floor collapses during an operation.
［ステップ２０２］
　原子炉建屋１０のオペレイティングフロア４０の天井クレーン２０を用いてＰＣＶ上部開口を塞ぐ蓋２２を設置する。
　ＢＳＷ１１を解体するフロアのうち最上階（Ｆ１）は、内側にＰＣＶ１２の壁面がないため、蓋２２を設置することによって壁撤去時にコンクリートガラがＰＣＶ１２内に落下することを防止でき、かつ放射性物質の拡散を防止できる。
［ステップ２０３］
　原子炉建屋１０の解体場所（各フロア）への解体装置の搬入に干渉する壁を撤去する。なおこの作業は必要に応じて行う。 [Step 202]
A lid 22 that closes the PCV upper opening is installed using the overhead crane 20 of the operating floor 40 of the reactor building 10.
Since the top floor (F1) of the floor where the BSW 11 is dismantled does not have the wall surface of the PCV 12 inside, it is possible to prevent the concrete glass from falling into the PCV 12 when the wall is removed by installing the lid 22, and of the radioactive material Diffusion can be prevented.
[Step 203]
The wall which interferes with carrying in of the demolition apparatus to the demolition place (each floor) of the reactor building 10 is removed. This work is performed as necessary.
［ステップ２０４］
　図５は解体対象フロアのうち最上階フロア（Ｆ１）のＢＳＷ非放射化部１１ｂの解体作業の説明図である。まず現場に解体装置２４を搬入する。図示の解体装置２４は、ブレーカを装着した小型重機である。なおＢＳＷ非放射化部１１ｂとＢＳＷ放射化部１１ａを分けて解体できる手法であれば採用工法はこれに限らず、この他にも例えばコンクリートカッターやワイヤーソーなどを適用することができる。また、解体装置２４は必ずしも遠隔操作式である必要はない。
［ステップ２０５］
　解体場所は、シート等による適切な養生２６や局所排気設備２８を設ける。これによりコンクリート破砕により発生する非放射性の粉塵や放射性粉塵による汚染が建物内に拡散することを防止できる。 [Step 204]
FIG. 5 is an explanatory view of the dismantling work of the BSW non-activation part 11b of the top floor (F1) among the dismantling target floors. First, the dismantling device 24 is carried into the site. The dismantling device 24 shown is a small heavy machine equipped with a breaker. Note that the adopted construction method is not limited to this as long as the BSW non-activation part 11b and the BSW activation part 11a can be disassembled separately, and for example, a concrete cutter, a wire saw, or the like can be applied. Further, the dismantling device 24 is not necessarily remote-controlled.
[Step 205]
In the dismantling place, an appropriate curing 26 using a sheet or the like and a local exhaust facility 28 are provided. As a result, it is possible to prevent non-radioactive dust generated by crushing concrete and contamination due to radioactive dust from diffusing into the building.
［ステップ２０６］
　養生完了後，ＢＳＷ非放射化部１１ｂを解体装置２４となる小型重機ではつって解体する。
［ステップ２０７］
　図６は解体したコンクリートガラの回収作業の説明図である。発生したガラは、ガラ回収用ショベル付重機３０でかき集めてガラ搬送台車３２に載せる。なお特に重機を使う必要はなく、人手によりガラを回収してガラ搬送台車３２へ積載することもできる。
　このとき、非放射性廃棄物への放射性廃棄物混入を防止するために、ガラの回収・台車積載と並行して、サーベイメータ等でガラの放射能測定を実施することが望ましい。ガラ搬送台車３２に積載したガラは図示しない保管場所へ移送される。なお、保管場所が原子炉建屋１０内の他のフロアあるいは原子炉建屋１０以外の場合には、ガラ搬送台車３２をオペレイティングフロア４０および各フロアと通じた開口部（不図示）まで移動して、天井クレーン２０で所定の場所まで吊り降ろしている。 [Step 206]
After the curing is completed, the BSW non-activation part 11b is disassembled by a small heavy machine that is the dismantling device 24.
[Step 207]
FIG. 6 is an explanatory view of the work of collecting the dismantled concrete glass. The generated glass is collected by a heavy machine 30 with an excavator for collecting glass and placed on a glass transport carriage 32. In addition, it is not necessary to use a heavy machine in particular, and it is also possible to collect the glass manually and load it on the glass transport carriage 32.
At this time, in order to prevent the radioactive waste from being mixed into the non-radioactive waste, it is desirable to measure the radioactivity of the glass with a survey meter or the like in parallel with the collection of the glass and the loading of the cart. The glass loaded on the glass transport carriage 32 is transferred to a storage location (not shown). When the storage location is other floor in the reactor building 10 or other than the reactor building 10, the glass carriage 32 is moved to the operating floor 40 and an opening (not shown) communicating with each floor. The crane is suspended to a predetermined place by the overhead crane 20.
［ステップ２０８］
　図７は最上階フロア（Ｆ１）のＢＳＷ非放射化部の一部解体後の説明図である。ＢＳＷ非放射化部１１ｂ解体で使った解体装置２４とガラ搬送台車３２を、ＢＳＷ放射化部１１ａ解体用の解体装置２４とガラ搬送台車３２に入れ替える。これによりＢＳＷ非放射化部１１ｂとＢＳＷ放射化部１１ａの間のコンタミを防止できる。
［ステップ２０９］
　その後、図５で解体した範囲より原子炉側の領域（ＢＳＷ放射化部１１ａ）のコンクリートを全て解体する。
［ステップ２１０］
　解体したコンクリートは、図５と同様、ガラ搬送台車３２で外部の保管場所へ搬出する。このとき並行してサーベイメータ等でガラの放射能測定を実施することが望ましい。 [Step 208]
FIG. 7 is an explanatory diagram after partial disassembly of the BSW non-activation part of the top floor (F1). The dismantling device 24 and the glass transport cart 32 used in the dismantling of the BSW non-activation unit 11b are replaced with the dismantling device 24 and the glass transport cart 32 for dismantling the BSW activation unit 11a. Thereby, the contamination between the BSW non-activation part 11b and the BSW activation part 11a can be prevented.
[Step 209]
Thereafter, all the concrete in the region on the reactor side (BSW activation portion 11a) is dismantled from the range disassembled in FIG.
[Step 210]
The demolished concrete is carried out to an external storage place by the glass transport cart 32 as in FIG. At this time, it is desirable to measure the radioactivity of the glass with a survey meter or the like in parallel.
［ステップ２１１］
　図８は下階フロアのＢＳＷ解体準備の説明図である。上階フロアのＢＳＷ解体が完了したら片付け・清掃し，解体装置２４等を天井クレーン２０で階下に下ろし移動する。また、以降、ＰＣＶ１２内へガラ落下のおそれがないため、蓋２２を天井クレーン２０で撤去する。
　なお解体装置２４を新たな解体場所に移動させる際、ＢＳＷ１１以外の壁が干渉する場合は、これらを撤去する。このとき撤去する壁は事前評価により建物強度に問題がないことが明らかになっているものとする。
　図９は下階フロアのＢＳＷ解体の説明図である。上階フロアと同じくまずは養生２６作業を実施してＢＳＷ非放射化部１１ｂを解体する。次いでＢＳＷ放射化部１１ａを解体する。以後、最下階フロアのＢＳＷ１１までステップ２０５～２１１の解体作業を繰り返す。 [Step 211]
FIG. 8 is an explanatory diagram of preparation for dismantling the BSW on the lower floor. When the BSW dismantling of the upper floor is completed, it is cleaned and cleaned, and the dismantling device 24 and the like are moved down by the overhead crane 20 and moved. Moreover, since there is no possibility of the glass falling into the PCV 12, the lid 22 is removed with the overhead crane 20.
In addition, when moving the dismantling apparatus 24 to a new dismantling place, when walls other than BSW11 interfere, these are removed. It is assumed that the wall to be removed at this time has no problem in building strength by prior evaluation.
FIG. 9 is an explanatory diagram of the BSW dismantling of the lower floor. As with the upper floor, first, curing 26 is performed to dismantle the BSW non-activation part 11b. Next, the BSW activation unit 11a is disassembled. Thereafter, the dismantling work in steps 205 to 211 is repeated up to BSW 11 on the lowest floor.
　図１０は全てのＢＳＷ放射化部およびＢＳＷ非放射化部撤去後の原子炉建屋の説明図である。図示のように原子炉周辺のコンクリート壁（ＢＳＷ）が撤去されている。このため、ＰＣＶ１２の外側からアクセス可能となっている。
　なお、これまで述べた解体手順では、あるフロアのＢＳＷ非放射化部１１ｂとＢＳＷ放射化部１１ａを連続して解体し、その後下階フロアの作業に移行していた。その他の手順として、各フロアのＢＳＷ非放射化部１１ｂの撤去が完了してからＢＳＷ放射化部１１ａの解体に着手してもよい。また同様に、上階フロアのＢＳＷ非放射化部１１ｂの解体作業が終了して下階フロアに移行するタイミングで、上階フロアのＢＳＷ放射化部１１ａを後追いで解体するような手順でも構わない。 FIG. 10 is an explanatory diagram of the reactor building after all BSW activation parts and BSW non-activation parts have been removed. As shown, the concrete wall (BSW) around the reactor has been removed. For this reason, it can be accessed from the outside of the PCV 12.
In the dismantling procedure described so far, the BSW non-activation part 11b and the BSW activation part 11a of a certain floor are successively disassembled, and then the operation moves to the lower floor work. As another procedure, the disassembly of the BSW activation unit 11a may be started after the removal of the BSW non-activation unit 11b on each floor is completed. Similarly, it is possible to follow up and dismantle the BSW activation unit 11a on the upper floor at the timing when the disassembly work of the BSW non-activation unit 11b on the upper floor is completed and the process moves to the lower floor. .
［ステップ３０］
　次にＰＣＶ１２を外側から解体作業を行う。
［ステップ３０１］
　図１１はＰＣＶ円筒部解体の説明図である。本実施形態のＰＣＶ解体は、一例として人手によるガス切断を採用し以下説明する。
　そこでまず切断作業を行うフロアおよびそれより上方に汚染拡散防止兼火気養生３４を施す。なお切断方法はガス切断に限らず、この他にもディスクカッター等による機械式切断などでもよい。また被曝低減を考慮する場合は、切断作業を遠隔化することでもよい。 [Step 30]
Next, the PCV 12 is disassembled from the outside.
[Step 301]
FIG. 11 is an explanatory view of the PCV cylindrical part disassembly. The PCV disassembly of this embodiment employs manual gas cutting as an example and will be described below.
Therefore, first, a contamination diffusion prevention / fire curing 34 is applied to the floor where the cutting operation is performed and above the floor. The cutting method is not limited to gas cutting, but may be mechanical cutting using a disk cutter or the like. Moreover, when considering reduction of exposure, the cutting work may be remoted.
［ステップ３０２］
　次に切断のためにＰＣＶ円筒部に寄り付くために作業用足場３６を作業するフロア上に組み立てて設置する。
［ステップ３０３］
　さらにＰＣＶ切断片を細かく切断するための解体装置２４を搬入する。
［ステップ３０４］
　上記準備ができたらまず、天井クレーン２０でＰＣＶ１２上方まで吊り降ろした吊上げ天秤３８にＰＣＶ１２の上部を玉掛けする。この吊上げ天秤３８は、ＰＣＶ円筒部１２ａの周方向を複数点玉掛け可能な構造となっている。玉掛け作業は作業用足場３６上から作業者がＰＣＶ１２に寄り付いて行えばよい。
　また吊上げ天秤３８とＰＣＶ１２の連結は、ＰＣＶ１２に仮設の吊点（不図示）を溶接等で取り付け、吊上げ天秤３８とＰＣＶ１２をワイヤーロープやチェーンブロックで連結するなどすればよい。 [Step 302]
Next, the work scaffold 36 is assembled and installed on the floor on which the work is performed in order to approach the PCV cylindrical portion for cutting.
[Step 303]
Further, a dismantling device 24 for finely cutting the PCV cut piece is carried in.
[Step 304]
When the above preparation is completed, first, the upper part of the PCV 12 is slung on the lifting balance 38 that is suspended to the upper side of the PCV 12 by the overhead crane 20. The lifting balance 38 has a structure in which a plurality of points can be hung in the circumferential direction of the PCV cylindrical portion 12a. The staking work may be performed by the worker approaching the PCV 12 from the work scaffold 36.
The lifting balance 38 and the PCV 12 may be connected by attaching a temporary lifting point (not shown) to the PCV 12 by welding or the like, and connecting the lifting balance 38 and the PCV 12 with a wire rope or a chain block.
［ステップ３０５］
　吊上げ天秤３８にＰＣＶ１２を玉掛け後、作業用足場３６上を作業者がＰＣＶ１２周方向に移動しながらガス切断し、ＰＣＶ１２をリング状に分割する。
［ステップ３０６］
　リング状の切断片は天井クレーン２０でオペレイティングフロア４０に吊上げて手作業で縦方向（円筒の軸芯方向）に４分割や６分割程度にガス切断で粗切りする。さらにそれを廃棄物収納容器４１に入る大きさにバンドソーなどの解体装置２４で細断する。廃棄物を収納した廃棄物収納容器４１は，図示しない容器の一時保管場所に移送される。 [Step 305]
After the PCV 12 is slung on the lifting balance 38, the operator cuts the gas while moving in the circumferential direction of the PCV 12 on the work scaffold 36, thereby dividing the PCV 12 into a ring shape.
[Step 306]
The ring-shaped cut pieces are lifted on the operating floor 40 by the overhead crane 20 and are roughly cut by gas cutting into four or six divisions in the vertical direction (axial direction of the cylinder) by hand. Furthermore, it is shredded by a dismantling device 24 such as a band saw into a size that fits into the waste container 41. The waste container 41 storing the waste is transferred to a temporary storage place for a container (not shown).
［ステップ３０７］
　作業フロアでのＰＣＶ１２のリング状の切断作業が終了したら、片付け・清掃を行い、下階フロアに移動する。
　上述のＰＣＶ円筒部１２ａの解体作業を各フロアで繰り返し、ＰＣＶ円筒部１２ａの解体を終了する。その後、ＰＣＶ球形部１２ｂの解体作業に移行する。
　図１２はＰＣＶ球形部の解体作業の説明図１である。図１３はＰＣＶ球形部の解体作業の説明図２である。図１４はＰＣＶ球形部の解体作業の説明図３である。ＰＣＶ球形部１２ｂは複雑形状なため、外周に足場を設けることが難しい。よってここでは高所作業台車４２でＰＣＶ１２付近までアクセスして切断作業を行う。また切断中のＰＣＶ球形部１２ｂを天井クレーン２０で吊るのも難しいため、ここでは上階フロアに配置した小型クレーン４４で吊りながら切断作業を行う。 [Step 307]
When the ring-shaped cutting operation of the PCV 12 on the work floor is completed, it is cleaned and cleaned and moved to the lower floor.
The above-described dismantling work of the PCV cylindrical portion 12a is repeated on each floor, and the disassembling of the PCV cylindrical portion 12a is completed. Thereafter, the process proceeds to the dismantling work of the PCV spherical portion 12b.
FIG. 12 is an explanatory view 1 of the dismantling work of the PCV spherical portion. FIG. 13 is an explanatory diagram 2 of the dismantling work of the PCV spherical portion. FIG. 14 is an explanatory diagram 3 of the dismantling work of the PCV spherical portion. Since the PCV spherical portion 12b has a complicated shape, it is difficult to provide a scaffold on the outer periphery. Therefore, here, the cutting work is performed by accessing the vicinity of the PCV 12 with the high work platform 42. Further, since it is difficult to suspend the PCV spherical portion 12b being cut by the overhead crane 20, the cutting work is performed while being suspended by the small crane 44 disposed on the upper floor.
［ステップ３０８］
　まず高所作業台車４２、小型クレーン４４を各作業フロアに移送する。その後、小型クレーン４４にＰＣＶ球形部１２ｂを玉掛けする。ここでＰＣＶ球形部１２ｂはリング状には切断しても寸法形状の関係からそのままオペレイティングフロア４０に上げることができない。このためＰＣＶ球形部１２ｂはある程度細かいパネル状に切断する。
［ステップ３０９］
　ＰＣＶ球形部１２ｂの切断箇所に高所作業台車４２で寄り付き、吊り点（不図示）を切断部位に溶接するなどしてこれを小型クレーン４４に玉掛けする。 [Step 308]
First, the high work platform 42 and the small crane 44 are transferred to each work floor. Thereafter, the PCV spherical portion 12 b is hung on the small crane 44. Here, even if the PCV spherical portion 12b is cut into a ring shape, the PCV spherical portion 12b cannot be raised to the operating floor 40 as it is because of the dimensional shape. For this reason, the PCV spherical portion 12b is cut into a fine panel shape to some extent.
[Step 309]
The high work platform 42 is brought close to the cut portion of the PCV spherical portion 12b, and a hanging point (not shown) is welded to the cut portion, for example, and this is hung on the small crane 44.
［ステップ３１０］
　玉掛け完了後、高所作業台車４２上からＰＣＶ球形部１２ｂを切断する。ここでは切断工法はＰＣＶ円筒部１２ａと同様にガス切断を適用する。
　そこで切断作業を行うフロアおよびそれより上方に汚染拡散防止兼火気養生３４を施す。なお切断方法はガス切断に限らず、この他にもディスクカッター等による機械式切断などでもよい。また被曝低減を考慮する場合は、切断作業を遠隔化することでもよい。
［ステップ３１１］
　切断後、小型クレーン４４で切断片を一旦ＰＣＶ１２の底部に吊り降ろす。
［ステップ３１２］
　次にＰＣＶ１２の底部に作業者が切断片を小型クレーン４４から取り外しして、天井クレーン２０に玉掛けし直してオペレイティングフロア４０に移動する。 [Step 310]
After the staking is completed, the PCV spherical portion 12b is cut from the high work platform 42. Here, the cutting method applies gas cutting in the same manner as the PCV cylindrical portion 12a.
Therefore, a contamination diffusion prevention / fire curing 34 is applied to the floor where the cutting operation is performed and above. The cutting method is not limited to gas cutting, but may be mechanical cutting using a disk cutter or the like. Moreover, when considering reduction of exposure, the cutting work may be remoted.
[Step 311]
After cutting, the cut piece is once suspended by the small crane 44 on the bottom of the PCV 12.
[Step 312]
Next, an operator removes a cut piece from the small crane 44 to the bottom of the PCV 12, hangs it on the overhead crane 20, and moves to the operating floor 40.
［ステップ３１３］
　その後、オペレイティングフロア４０で切断片を細断して廃棄物収納容器４１に収納し、廃棄物収納容器４１を保管場所まで移動する。
［ステップ３１４］
　作業フロアでの作業が終了したら、片付け・清掃を行い、小型クレーン４４を下階フロアに移して（図１３，１４参照）次の解体作業を行う。ステップ３０８～３１４を繰返し、ＰＣＶ球形部１２ｂの解体作業を完了する。
［ステップ４０］
　全て放射性廃棄物撤去完了後、管理区域を解除する。 [Step 313]
Thereafter, the cut pieces are shredded and stored in the waste storage container 41 on the operating floor 40, and the waste storage container 41 is moved to the storage location.
[Step 314]
When the work on the work floor is completed, cleaning and cleaning are performed, the small crane 44 is moved to the lower floor (see FIGS. 13 and 14), and the next dismantling work is performed. Steps 308 to 314 are repeated to complete the disassembly work of the PCV spherical portion 12b.
[Step 40]
After all radioactive waste is removed, the controlled area will be released.
［ステップ５０］
　残りの原子炉建屋１０の建物コンクリートを解体する。
　このような本発明の原子炉格納容器及び生体遮蔽壁の解体工法によれば、高所作業がなくなりＰＣＶ及びＢＳＷの解体撤去作業の安全性を高めることができる。
　以上、本発明の好ましい実施形態について説明した。しかしながら、本発明は、上記実施形態に何ら制限されることなく、本発明の主旨を逸脱しない範囲において、種々の変更が可能である。
　また、本発明は、実施形態において示された組み合わせに限定されることなく、種々の組み合わせによって実施可能である。例えば、炉内構造物、原子炉圧力容器、熱遮蔽壁を解体した原子炉建屋のみに適用するとの限定は必須でなはく、ＢＳＷ、ＰＣＶをフロア側から解体する工法としても良い。 [Step 50]
The building concrete of the remaining reactor building 10 is dismantled.
According to the reactor containment vessel and the biological shielding wall dismantling method of the present invention, it is possible to increase the safety of dismantling / removing work of PCV and BSW because there is no work at high places.
The preferred embodiments of the present invention have been described above. However, the present invention is not limited to the above embodiment, and various modifications can be made without departing from the spirit of the present invention.
Moreover, the present invention is not limited to the combinations shown in the embodiments, and can be implemented by various combinations. For example, it is not essential to apply only to the reactor building in which the reactor internal structure, the reactor pressure vessel, and the heat shield wall are disassembled, and the BSW and PCV may be dismantled from the floor side.
　本発明は、耐用年数の経過した原子力発電所の廃炉作業を行う原子力産業分野において産業上の利用可能性を有する。 The present invention has industrial applicability in the nuclear industry field where the decommissioning work of a nuclear power plant that has passed its useful life has been carried out.
１０………原子炉建屋、１１………生体遮蔽壁（ＢＳＷ）、１１ａ………ＢＳＷ放射化部、１１ｂ………ＢＳＷ非放射化部、１２………原子炉格納容器（ＰＣＶ）、１２ａ………ＰＣＶ円筒部、１２ｂ………ＰＣＶ球形部、１４………原子炉圧力容器（ＲＰＶ）、１５………炉内構造物、１６………熱遮蔽壁（ＲＳＷ）、１８………仮設補強部材、２０………天井クレーン、２２………蓋、２４………解体装置、２６………養生、２８………局所排気設備、３０………ガラ回収用ショベル付重機、３２………ガラ搬送台車、３４………汚染拡散防止兼火気養生、３６………作業用足場、３８………吊上げ天秤、４０………オペレイティングフロア、４１………廃棄物収納容器、４２………高所作業台車、４４………小型クレーン。 10 ......... Reactor building, 11 ......... Biological shielding wall (BSW), 11a ......... BSW activation part, 11b ......... BSW non-activation part, 12 ......... Reactor containment vessel (PCV), 12a ... PCV cylindrical part, 12b ... PCV spherical part, 14 ... Reactor pressure vessel (RPV), 15 ... Reactor structure, 16 ... Heat shield wall (RSW), 18 ... ...... Temporary reinforcement member, 20 ......... Overhead crane, 22 ......... Cover, 24 ......... Dismantling device, 26 ......... Hardening, 28 ......... Local exhaust equipment, 30 ......... Excavator heavy machine with waste collection 32 ......... Galaxy transport cart 34 ......... Contamination prevention and fire curing 36 ......... Working scaffolding 38 ......... Lifting balance 40 ......... Operating floor 41 ......... Waste storage Container, 42 ......... Aerial work platform, 44 ......... Small crane.

Claims (9)

  1. 　原子炉建屋の各フロア側から生体遮蔽壁を解体するＢＳＷ解体工程と、
    　前記生体遮蔽壁を解体したフロア側から原子炉格納容器を解体するＰＣＶ解体工程と、
    　を有することを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法。     BSW dismantling process for dismantling the biological shielding wall from each floor side of the reactor building,
    A PCV dismantling step of dismantling the reactor containment vessel from the floor side dismantling the biological shielding wall;
    A reactor containment vessel and a biological shielding wall dismantling method characterized by comprising:
  2. 　炉内構造物と原子炉圧力容器と熱遮蔽壁を解体した原子炉建屋の各フロア側から生体遮蔽壁を解体するＢＳＷ解体工程と、
    　前記生体遮蔽壁を解体したフロア側から原子炉格納容器を解体するＰＣＶ解体工程と、
    　を有することを特徴とする原子炉格納容器及び生体遮蔽壁の解体工法。     BSW dismantling process of dismantling the biological shielding wall from each floor side of the reactor building where the reactor internal structure, the reactor pressure vessel, and the heat shielding wall are dismantled;
    A PCV dismantling step of dismantling the reactor containment vessel from the floor side dismantling the biological shielding wall;
    A reactor containment vessel and a biological shielding wall dismantling method characterized by comprising:
  3. 　前記生体遮蔽壁を解体する前に各フロアを仮設補強部材で補強することを特徴とする請求項１又は２に記載の原子炉格納容器及び生体遮蔽壁の解体工法。 The method of disassembling a reactor containment vessel and a biological shielding wall according to claim 1 or 2, wherein each floor is reinforced with a temporary reinforcing member before the biological shielding wall is disassembled.
  4. 　前記ＢＳＷ解体工程の前に前記原子炉格納容器の上面開口を蓋で塞ぐことを特徴とする請求項１ないし３のいずれか１に記載の原子炉格納容器及び生体遮蔽壁の解体工法。 The reactor containment vessel and biological shielding wall dismantling method according to any one of claims 1 to 3, wherein a top opening of the reactor containment vessel is closed with a lid before the BSW disassembly step.
  5. 　前記ＢＳＷ解体工程は、ＢＳＷ非放射化部を解体した後にＢＳＷ放射化部を解体し、前記ＢＳＷ放射化部の解体作業前に解体装置を換えることを特徴とする請求項１ないし４のいずれか１に記載の原子炉格納容器及び生体遮蔽壁の解体工法。 5. The BSW disassembly step includes disassembling the BSW activation part after disassembling the BSW non-activation part, and changing the disassembly apparatus before the disassembly work of the BSW activation part. The reactor containment vessel and the biological shielding wall dismantling method according to 1.
  6. 　前記ＰＣＶ解体工程は、ＰＣＶ円筒部を上階のフロアから順番に各フロアでリング状に切断した後、オペレイティングフロアへ搬出して細分化することを特徴とする請求項１ないし５のいずれか１に記載の原子炉格納容器及び生体遮蔽壁の解体工法。 6. The PCV dismantling step is characterized in that the PCV cylindrical portion is cut into a ring shape on each floor in order from the upper floor, and then carried out to the operating floor to be subdivided. The reactor containment vessel and the biological shielding wall dismantling method according to 1.
  7. 　前記ＰＣＶ円筒部は、切断作業前に天井クレーンで玉掛けすることを特徴とする請求項６に記載の原子炉格納容器及び生体遮蔽壁の解体工法。 The reactor containment vessel and biological shielding wall dismantling method according to claim 6, wherein the PCV cylindrical portion is slung with an overhead crane before cutting work.
  8. 　前記ＰＣＶ解体工程は、ＰＣＶ球形部を各フロアで小片化した後、オペレイティングフロアへ搬出して細分化することを特徴とする請求項１ないし７のいずれか１に記載の原子炉格納容器及び生体遮蔽壁の解体工法。 The reactor containment vessel according to any one of claims 1 to 7, wherein the PCV dismantling step includes dividing the PCV spherical portion into pieces on each floor, and then carrying out the pieces to the operating floor and subdividing them. Demolition method of biological shielding wall.
  9. 　前記ＰＣＶ球形部は、切断作業前に小型クレーンで玉掛けすることを特徴とする請求項８に記載の原子炉格納容器及び生体遮蔽壁の解体工法。 The reactor containment vessel and biological shielding wall dismantling method according to claim 8, wherein the PCV spherical portion is slung with a small crane before cutting work.
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Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS56111764A (en) * 1980-02-06 1981-09-03 Toda Construction Method of overhauling construction of cylindrical concrete structure* inside thereof has vessel in steel plate
JPH0194164A (en) * 1987-10-05 1989-04-12 Kajima Corp Method of cutting overhaul construction of cylindrical structure
JPH04158297A (en) * 1990-10-22 1992-06-01 Takenaka Komuten Co Ltd Cutting out of large sized block of activation part in biological shielding structure of nuclear reactor
JP2005083923A (en) * 2003-09-09 2005-03-31 Ohbayashi Corp Demolishing method of biological shield wall
JP2012230084A (en) * 2011-04-27 2012-11-22 Shimizu Corp Method for dismantling nuclear power generation plant building
JP2014098570A (en) * 2012-11-13 2014-05-29 Shimizu Corp Opening formation method

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS56111764A (en) * 1980-02-06 1981-09-03 Toda Construction Method of overhauling construction of cylindrical concrete structure* inside thereof has vessel in steel plate
JPH0194164A (en) * 1987-10-05 1989-04-12 Kajima Corp Method of cutting overhaul construction of cylindrical structure
JPH04158297A (en) * 1990-10-22 1992-06-01 Takenaka Komuten Co Ltd Cutting out of large sized block of activation part in biological shielding structure of nuclear reactor
JP2005083923A (en) * 2003-09-09 2005-03-31 Ohbayashi Corp Demolishing method of biological shield wall
JP2012230084A (en) * 2011-04-27 2012-11-22 Shimizu Corp Method for dismantling nuclear power generation plant building
JP2014098570A (en) * 2012-11-13 2014-05-29 Shimizu Corp Opening formation method

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
MITSUI, HIDEHIKO: "Current status and issues of decommissioning technology III, Systems engineering", JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, vol. 33, no. 5, 1991, pages 415 - 418 *
SEIKI, YOSHIHIRO ET AL.: "JPDR dismantling project - JPDR facilities and dismantling of equipment", JOURNAL OF THE RANDEC, 15 December 1996 (1996-12-15), pages 12 - 23 *

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