JPH0229199B2 - - Google Patents

Info

Publication number
JPH0229199B2
JPH0229199B2 JP57195961A JP19596182A JPH0229199B2 JP H0229199 B2 JPH0229199 B2 JP H0229199B2 JP 57195961 A JP57195961 A JP 57195961A JP 19596182 A JP19596182 A JP 19596182A JP H0229199 B2 JPH0229199 B2 JP H0229199B2
Authority
JP
Japan
Prior art keywords
cutting
cut
rpv
pressure vessel
reactor pressure
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
JP57195961A
Other languages
Japanese (ja)
Other versions
JPS5987400A (en
Inventor
Keizo Harada
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Mitsubishi Power Ltd
Original Assignee
Babcock Hitachi KK
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 Babcock Hitachi KK filed Critical Babcock Hitachi KK
Priority to JP57195961A priority Critical patent/JPS5987400A/en
Publication of JPS5987400A publication Critical patent/JPS5987400A/en
Publication of JPH0229199B2 publication Critical patent/JPH0229199B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Working Measures On Existing Buildindgs (AREA)
  • Processing Of Solid Wastes (AREA)

Description

【発明の詳細な説明】 〔発明の利用分野〕 この発明は、原子炉の廃炉に係り、特に原子炉
圧力容器(以下、RPVと記す)の切断解体を効
率よく行う方式に関するものである。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to the decommissioning of nuclear reactors, and particularly to a method for efficiently cutting and disassembling a reactor pressure vessel (hereinafter referred to as RPV).

〔従来技術〕[Prior art]

第1図イに示すように、従来、RPV1の切断
解体は、プラズマアークによつてRPV1を直接
細切断し、図示してない燃料プールでパツケージ
に収納して搬出していた。しかし、この方式は、
第1図ロに示すように、RPV1の(1個の輪切
り円周の長さb)×(輪切りの個数−1)の長さに
加えて(輪切りの幅a)×(1個の輪切りにおける
細切断物6の数)×(輪切りの個数)の長さだけ切
断しなければならないため、輪切りのみ行う場合
の約2倍の長さの切断を行う必要があつた。廃炉
においてRPV1を切断、解体するときは、該
RPV1の周りに500mR/h以上の照射線量率が
あるため、マニピユレータ3に切断トーチ2を取
付けた完全な自動遠隔操作によつて切断作業を行
なつているが、このような高照射線量率の場所に
おいて長時間、上記の複雑な切断作業をしなけれ
ばならないため、上記マニピユレータ3、切断ト
ーチ2等からなる切断機が故障すると、その修理
にかなりの工数を要するとともに(上記のように
複雑な作業を長時間行うと当然故障の確率が高く
なる)、RPV1の切断位置が水面4より上部の空
気中であるため、ヒユームが多量に発生するとい
う欠点があつた。なお、図中、5は吊り金具用
穴、7はサービスフロアを示す。
As shown in FIG. 1A, conventionally, the RPV 1 was cut and dismantled by directly cutting the RPV 1 into pieces using a plasma arc, storing it in a package in a fuel pool (not shown), and transporting it. However, this method
As shown in FIG. Since it was necessary to cut the length equal to (number of thinly cut objects 6) x (number of round slices), it was necessary to cut approximately twice as long as when only round cutting was performed. When cutting and dismantling RPV1 during decommissioning, the applicable
Since the area around the RPV 1 has an irradiation dose rate of 500 mR/h or more, the cutting work is performed by fully automatic remote control using a cutting torch 2 attached to the manipulator 3. Because the above-mentioned complicated cutting work has to be performed at a location for a long time, if the cutting machine consisting of the above-mentioned manipulator 3, cutting torch 2, etc. breaks down, it will take a considerable amount of man-hours to repair it (as above-mentioned complicated cutting work). (Of course, if the work is done for a long time, the probability of failure increases.) Since the cutting position of RPV 1 is in the air above the water surface 4, there is a drawback that a large amount of fume is generated. In the figure, 5 indicates a hole for a hanging metal fitting, and 7 indicates a service floor.

〔発明の目的〕[Purpose of the invention]

この発明の目的は、上記した従来技術の欠点を
なくし、RPVの切断解体を効率よく行ない、か
つヒユーム等の発生を低減し得る切断方式を提供
するにある。
An object of the present invention is to provide a cutting method that eliminates the drawbacks of the prior art described above, efficiently cuts and disassembles an RPV, and reduces the generation of fumes.

〔発明の概要〕[Summary of the invention]

要するにこの発明は、RPVの設置位置におい
て、該RPVの輪切り切断を行ない、照射線量率
の低い使用済み燃料プール中で細切断してパツケ
ージに収納し搬出する切断方式であり、かつ、切
断時のヒユームを水に吸収させるために切断位置
をRPV内の水面と一致させて切断し、上記燃料
プール内では水中において切断を行う方式であ
る。
In short, this invention is a cutting method in which the RPV is cut into rounds at the RPV installation location, cut into small pieces in a spent fuel pool with a low irradiation dose rate, stored in a package cage, and transported. In order to absorb the fume into the water, the cutting position is aligned with the water surface inside the RPV, and the cutting is done underwater in the fuel pool.

〔発明の実施例〕[Embodiments of the invention]

以下、この発明の一実施例を第2図に基づいて
説明する。なお、第1図と同一または同等の部位
には同一の符号を付ける。該第2図は、原子力発
電所に設置されている廃炉のRPV1を切断、解
体する概念図を示すもので、第2図イに示すよう
にRPV1の上記設置状態において、該RPV1を
切断トーチ2により水面4と一致した個所を輪切
りにして輪切り切断物8を得、第2図ロに示すよ
うに、該輪切り切断物8に設けた吊り金具用穴5
に吊り金具9を引掛けて、ワイヤロープ10によ
り第1図イの矢印c方向に吊り上げ、矢印d方向
へ移送して、RPV1に隣設した照射線量率の低
い燃料プール11の水中に矢印eに示すように吊
り下げて、該燃料プール11の底部に静置してか
ら、切断トーチ2により軸方向に細切断する。こ
のようにして得られる細切断物6は、燃料プール
11内において図示してないパツケージに収納し
て搬出する。
Hereinafter, one embodiment of the present invention will be described based on FIG. 2. Note that the same or equivalent parts as in FIG. 1 are given the same reference numerals. Figure 2 shows a conceptual diagram of cutting and disassembling the decommissioned RPV1 installed in a nuclear power plant. 2, the part that coincides with the water surface 4 is sliced into rings to obtain a round cut piece 8, and as shown in FIG.
Hook the hanging fitting 9 to the wire rope 10, lift it up in the direction of arrow c in FIG. After hanging the fuel as shown in FIG. 1 and leaving it stationary at the bottom of the fuel pool 11, the cutting torch 2 is used to cut the fuel into small pieces in the axial direction. The shredded material 6 thus obtained is stored in a package (not shown) in the fuel pool 11 and carried out.

この発明の他の実施例として第2図イに破線で
示したような方式がある。RPV1は、軟鉄の胴
体の内面にステンレスコーテイングを施してある
ため、上記実施例のように切断トーチ2によつて
RPV1の内面から輪切り切断する方式は多少切
断時間が長くかかる。そのため、この実施例のよ
うにRPV1の外側からマニピユレータ3′および
切断トーチ2′によつて切断または吊り金具用穴
5をあける方が作業時間が短くて済む。
Another embodiment of the present invention is the system shown by the broken line in FIG. 2A. Since the RPV1 has a stainless steel coating on the inner surface of its soft iron body, it can be cut with the cutting torch 2 as in the above embodiment.
The method of cutting into rings from the inner surface of RPV1 takes a little longer to cut. Therefore, it takes less time to cut or make the hole 5 for the hanging fixture from the outside of the RPV 1 using the manipulator 3' and the cutting torch 2' as in this embodiment.

この発明の第3の実施例としては、上記燃料プ
ール11の水中で輪切り切断物8を細切断する方
式と同様に、該輪切り切断物8を密閉したドライ
ヤセパレータプール内に移送した後、該ドライヤ
セパレータ内において上記輪切り切断物8を細切
断する方式である。
As a third embodiment of the present invention, similarly to the method in which the cut pieces 8 are cut into small pieces underwater in the fuel pool 11, the cut pieces 8 are transferred to a sealed dryer separator pool, and then the cut pieces 8 are transferred to the dryer separator pool. This is a method in which the round cut object 8 is cut into small pieces within a separator.

〔発明の効果〕〔Effect of the invention〕

照射線量率の高い場所における切断作業が、一
平面内における輪切り作業のみになるため、切断
長さが従来の場合の約1/2となり、遠隔操作作業
が簡単かつ作業時間が短縮できるとともに、作業
の信頼性が向上するという効果がある。
Cutting work in areas with high radiation dose rates is limited to circular cutting within a single plane, so the cutting length is approximately 1/2 that of conventional methods, making remote control work easier and reducing work time. This has the effect of improving reliability.

またRPVの輪切り切断位置を水面と一致させ
たことにより、上記切断によつて発生するヒユー
ムの一部が水に吸収されるため、サービスフロア
の方に上つてくるヒユーム量が少なくなるので、
該サービスフロアにおける空調換気系の設備が節
減できるという効果がある。
In addition, by aligning the RPV's cutting position with the water surface, some of the fume generated by the cutting is absorbed by the water, reducing the amount of fume that rises to the service floor.
This has the effect of saving air conditioning and ventilation system equipment on the service floor.

さらに燃料プール内における輪切り切断物の細
切断は水中で行うため、全切断作業の約50%が水
中切断となるから、ヒユーム等の発生量が従来の
方式に比して極めて少なくなるという効果があ
る。
Furthermore, since the cutting of the round pieces in the fuel pool is done underwater, approximately 50% of the total cutting work is underwater cutting, which has the effect of significantly reducing the amount of fumes generated compared to conventional methods. be.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は、原子炉の廃炉におけるRPV切断時
の従来の概念図、第2図は、この発明による上記
RPV切断時の概念図を示す。 符号の説明、1……RPV、2……切断トーチ、
3……マニピユレータ、6……細切断物、7……
サービスフロア、8……輪切り切断物、11……
燃料プール。
Fig. 1 is a conceptual diagram of the conventional RPV disconnection during decommissioning of a nuclear reactor, and Fig. 2 is a conceptual diagram of the above method according to the present invention.
A conceptual diagram of RPV disconnection is shown. Explanation of symbols, 1...RPV, 2...cutting torch,
3... Manipulator, 6... Shredded object, 7...
Service floor, 8...Cut into rings, 11...
fuel pool.

Claims (1)

【特許請求の範囲】[Claims] 1 原子炉の廃炉における原子炉圧力容器切断解
体方式において、原子炉圧力容器に水を入れ、切
断位置と水面とを一致させて該原子炉圧力容器を
輪切りにし、これを使用済み燃料プールまたはド
ライヤセパレータプール内に移送した後、細切断
し、パツケージに収納、搬出することを特徴とす
る原子炉の廃炉における原子炉圧力容器切断解体
方式。
1. In the reactor pressure vessel cutting and disassembly method for decommissioning a nuclear reactor, water is poured into the reactor pressure vessel, the cutting position is aligned with the water surface, the reactor pressure vessel is cut into rings, and the slices are placed in the spent fuel pool or A method for cutting and dismantling a nuclear reactor pressure vessel during decommissioning of a nuclear reactor, which is characterized by transferring it into a dryer separator pool, cutting it into pieces, storing it in a package, and transporting it.
JP57195961A 1982-11-10 1982-11-10 Cutting and dismantling system for pressure vessel in waste reactor Granted JPS5987400A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57195961A JPS5987400A (en) 1982-11-10 1982-11-10 Cutting and dismantling system for pressure vessel in waste reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57195961A JPS5987400A (en) 1982-11-10 1982-11-10 Cutting and dismantling system for pressure vessel in waste reactor

Publications (2)

Publication Number Publication Date
JPS5987400A JPS5987400A (en) 1984-05-19
JPH0229199B2 true JPH0229199B2 (en) 1990-06-28

Family

ID=16349860

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57195961A Granted JPS5987400A (en) 1982-11-10 1982-11-10 Cutting and dismantling system for pressure vessel in waste reactor

Country Status (1)

Country Link
JP (1) JPS5987400A (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6178986A (en) * 1984-09-21 1986-04-22 松下電工株式会社 Filling of dual-layered glass with gas
JPS61112299U (en) * 1984-12-26 1986-07-16
JP6337410B1 (en) * 2017-08-02 2018-06-06 株式会社日立プラントコンストラクション Reactor pressure vessel dismantling method
JP6788570B2 (en) * 2017-12-14 2020-11-25 日立Geニュークリア・エナジー株式会社 How to dismantle the reactor pressure vessel
KR102192100B1 (en) * 2019-02-14 2020-12-16 한국수력원자력 주식회사 Method for decommissioning nuclear facilities in water

Also Published As

Publication number Publication date
JPS5987400A (en) 1984-05-19

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