JPS5975199A - Method of cutting and dismantling reactor pressure vessel - Google Patents

Method of cutting and dismantling reactor pressure vessel

Info

Publication number
JPS5975199A
JPS5975199A JP57184465A JP18446582A JPS5975199A JP S5975199 A JPS5975199 A JP S5975199A JP 57184465 A JP57184465 A JP 57184465A JP 18446582 A JP18446582 A JP 18446582A JP S5975199 A JPS5975199 A JP S5975199A
Authority
JP
Japan
Prior art keywords
cutting
pressure vessel
reactor pressure
cut
stainless steel
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
JP57184465A
Other languages
Japanese (ja)
Other versions
JPH0229200B2 (en
Inventor
敬三 原田
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 JP57184465A priority Critical patent/JPS5975199A/en
Publication of JPS5975199A publication Critical patent/JPS5975199A/en
Publication of JPH0229200B2 publication Critical patent/JPH0229200B2/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)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 本発明は原子力発電所において廃炉とする原子炉圧力容
器を切断して解体する原子炉圧力容器の切断・解体方法
に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for cutting and disassembling a reactor pressure vessel to be decommissioned in a nuclear power plant.

原子力発電所において、原子炉を廃炉とする場合は原子
炉圧力容器を切断して解体することにより行なう。この
切断は従来、容器の内側から行なわれていた。
When decommissioning a nuclear reactor at a nuclear power plant, the reactor pressure vessel is cut and dismantled. Traditionally, this cutting was done from inside the container.

第1図は従来の切断・解体方法?示す原子炉断面図であ
る。
Is Figure 1 the conventional cutting and dismantling method? FIG.

図で、1は原子炉圧力容器を示し、1aはその胴体フラ
ンジ部である。2は原子炉圧力容器1の耐蝕性を維持す
るためその内側に構成されたステンレスクラッド、3は
原子炉圧力容器1を囲み放射線を遮蔽するγ遮蔽体、4
は原子炉圧力容器1内に注入された水である。5は原子
炉圧力容器1内に挿入されたマニプレータ、6はマニプ
レータ5に取付けられた切断トーチである。
In the figure, 1 indicates a reactor pressure vessel, and 1a is its fuselage flange. 2 is a stainless steel clad constructed inside the reactor pressure vessel 1 to maintain its corrosion resistance; 3 is a γ shield that surrounds the reactor pressure vessel 1 and shields radiation; 4
is the water injected into the reactor pressure vessel 1. 5 is a manipulator inserted into the reactor pressure vessel 1, and 6 is a cutting torch attached to the manipulator 5.

原子炉圧力容器1の切断は、まず、内部構造な除去され
た容器1内に水を張り、マニプレータ5な操作して切断
トーチ6を容器1の内壁に沿って移動させろことにより
行なわれろ。このような切断に際しては、内側にステン
レスクラッド2が張られているため、酸素アセチレンガ
ス切断法では切断できない。したがって、原子炉圧力容
器の切断には従来、次のような切断方法が考えられ℃い
た。
The cutting of the reactor pressure vessel 1 is carried out by first filling water into the vessel 1 from which the internal structure has been removed, and operating the manipulator 5 to move the cutting torch 6 along the inner wall of the vessel 1. In such cutting, since the stainless steel clad 2 is placed on the inside, the oxygen acetylene gas cutting method cannot be used. Therefore, conventionally, the following cutting methods have been considered for cutting the reactor pressure vessel.

(1)、プラズマアーク切断法により切断する。(1) Cutting by plasma arc cutting method.

(2)、ステンレスクラッド2をアークガウジング法に
より除去した後、酸素アセチレンガス切断法により切断
する。
(2) After removing the stainless steel cladding 2 by an arc gouging method, it is cut by an oxyacetylene gas cutting method.

(3)、ステンレスクラッド2をも同時に切断すること
ができるアーク鋸切断法により切断する。
(3) The stainless steel cladding 2 is cut using an arc saw cutting method that can also cut the stainless steel cladding 2 at the same time.

ところで、(1)のプラズマアーク切断法は、その切断
可能の最大厚みが150mmであるのに対して、商業炉
用原子炉圧力容器の板厚は300mm以上あるため、現
在の技術では切断することはでとず、使用不能である。
By the way, with the plasma arc cutting method (1), the maximum thickness that can be cut is 150 mm, whereas the thickness of the reactor pressure vessel for commercial reactors is 300 mm or more, so current technology cannot cut it. It is completely unusable.

又、(2)のアークガウジング法と酸素アセチレンガス
切断法、および(3)のアーク鋸切断法はいずれも安定
性、信頼性に欠けろという欠点がある。
Further, the arc gouging method and oxygen acetylene gas cutting method (2), and the arc saw cutting method (3) all have the drawback of lacking stability and reliability.

本発明の目的は、上記従来技術の欠点を除き、原子炉圧
力容器を遠隔操作により信頼性良く、安定して切断・解
体することができろ原子炉圧力容器の切断・解体方法を
提供するVrある。
An object of the present invention is to provide a method for cutting and dismantling a nuclear reactor pressure vessel, which eliminates the drawbacks of the above-mentioned prior art and allows the reactor pressure vessel to be cut and dismantled reliably and stably by remote control. be.

この目的を達成するため、本発明は、原子炉圧力容器内
に、その切断予定線の近くまで水を張り、原子炉圧力容
器の外側から、遠隔操作されるガス切断トーチを用いて
当該容器の外壁鋼板を切断し、その酸化熱により容器内
側に張られたステンレスクラッドをも切断可能状態とし
て切断するようにしたことを特徴とする。
In order to achieve this objective, the present invention fills the reactor pressure vessel with water up to the vicinity of the planned cutting line, and uses a remotely controlled gas cutting torch from outside the reactor pressure vessel to cut the vessel. It is characterized in that the outer wall steel plate is cut, and the stainless steel cladding placed inside the container can also be cut using the oxidation heat.

以下、本発明を図示の実施例に基づいて説−明する。The present invention will be explained below based on the illustrated embodiments.

第2図および第3図は本発明の一実施例に係る原子炉圧
力容器の切断・解体方法を示す原子炉断面図である。
FIGS. 2 and 3 are cross-sectional views of a nuclear reactor showing a method for cutting and disassembling a reactor pressure vessel according to an embodiment of the present invention.

第2図および第3図において、第1図に示す部分と同一
部分には同一符号が付されている。7は原子炉に設けら
れているサービスフロアである。
In FIGS. 2 and 3, the same parts as those shown in FIG. 1 are given the same reference numerals. 7 is a service floor provided in the nuclear reactor.

本実施例においては、このサービスフロア7に遠隔操作
されるマニプレータ2が設置され、その設置位置は、マ
ニプレータ2に取付けられている切断トーチ6が原子炉
圧力容器1の外壁に対向する位置とされろ。8は原子炉
圧力容器1が切断される切断予定線を示す。
In this embodiment, a remote-controlled manipulator 2 is installed on the service floor 7, and the installation position is such that the cutting torch 6 attached to the manipulator 2 faces the outer wall of the reactor pressure vessel 1. reactor. 8 indicates a planned cutting line along which the reactor pressure vessel 1 is cut.

まず、原子炉圧力容Bl内に水4が切断予定線80近く
まで張られろ。次に切断トーチ6に酸素アセチレンガス
を送り、これに点火して原子炉圧力容器1の外側の鋼板
を切断してゆく。この切断中、外側鋼板は高い酸化熱を
発生し、この熱により内側に設けられたステンレスクラ
ッド2が加熱されて切断可能状態となる。したがって、
酸素アセチレンガスにより外側鋼板と内側ステンレスク
ラッド2を一緒に切断することができる。切断中に吹糎
飛ばされたノロやドロスは水4内に落下して冷却される
。マニプレータ5を遠隔操作し、切断予定線8vc沿っ
て切断トーチ6を移動させろことにより原子炉圧力容器
1の胴体フランジ部1aを切断することができろ。切断
された胴体フランジ部1aを除去した後は第3図に示す
ように、マニプレータ5、切断トーチ6を原子炉圧力容
器lとr遮蔽体3の間に挿入し、新らたな切断予定線8
に沿って、引き続錠原子炉圧力容器1の胴体が切断され
ることとなる。
First, water 4 is filled in the reactor pressure volume Bl up to near the planned cutting line 80. Next, oxygen acetylene gas is sent to the cutting torch 6, which is ignited to cut the steel plate outside the reactor pressure vessel 1. During this cutting, the outer steel plate generates high oxidation heat, and this heat heats the stainless steel clad 2 provided on the inside, making it ready for cutting. therefore,
The outer steel plate and the inner stainless steel cladding 2 can be cut together using oxygen acetylene gas. Slag and dross blown away during cutting fall into the water 4 and are cooled. By remotely controlling the manipulator 5 and moving the cutting torch 6 along the planned cutting line 8vc, the fuselage flange portion 1a of the reactor pressure vessel 1 can be cut. After removing the cut fuselage flange part 1a, as shown in FIG. 8
The body of the lock reactor pressure vessel 1 will then be cut along this line.

このように、本実施例では、原子炉圧力容器の切断を容
器外側から行ない、外側鋼板の切断中に発生する酸化熱
により内側ステンレスクラッドを加熱して切断可能状態
とすることができるので、切断方法としては最も安定で
信頼性のある酸素アセチレンガスの使用が可能となり、
安定した信頼性ある原子炉圧力容器の切断・解体を行う
ことができる。又、酸素アセチレンガスの切断トーチは
他の切断機に比べて軽量であるので、マニプレータによ
る遠隔操作も容易になる。
As described above, in this embodiment, the reactor pressure vessel is cut from the outside of the vessel, and the oxidation heat generated during cutting of the outer steel plate can heat the inner stainless steel cladding to a state where it can be cut. As a method, it is possible to use oxygen acetylene gas, which is the most stable and reliable method.
It is possible to perform stable and reliable cutting and dismantling of nuclear reactor pressure vessels. Furthermore, since the oxygen-acetylene gas cutting torch is lighter than other cutting machines, remote control using a manipulator is also facilitated.

第4図は本発明の他の実施例に係る原子炉圧力容器の切
断・解体方法を示す原子炉断面図である。
FIG. 4 is a sectional view of a nuclear reactor showing a method for cutting and disassembling a reactor pressure vessel according to another embodiment of the present invention.

第4図で第2図および第3図に示す部分と同一部分には
同一符号が付されている。9は原子炉圧力容器1とγ遮
蔽体3との間に注入された水である。水9の注入は、γ
遮蔽体3の開口部な水密に封じることにより可能となる
。本実施例においても、切断はさぎの実施例と同様容器
外側から酸素アセチレンガスを用いて行なわれる。原子
炉圧力容器1の胴体フランジ部1aが切断除去された後
、マニプレータ5と切断トーチ6は原子炉圧力容器1と
γ遮蔽体3の間に挿入されて次の胴体部の切断・解体な
行なうのであるが、本実施例においては、新らたな切断
予定線8より上に水9を張ることにより、切断トーチ6
を水中に没し、胴体部の切断を水中で行なうようにする
ものである。
The same parts in FIG. 4 as those shown in FIGS. 2 and 3 are given the same reference numerals. 9 is water injected between the reactor pressure vessel 1 and the γ shield 3. The injection of water 9 is γ
This is possible by sealing the opening of the shield 3 watertight. In this example as well, the cutting is carried out from outside the container using oxygen acetylene gas, as in the case of the rabbit example. After the fuselage flange portion 1a of the reactor pressure vessel 1 is cut and removed, the manipulator 5 and the cutting torch 6 are inserted between the reactor pressure vessel 1 and the gamma shield 3 to cut and dismantle the next fuselage part. However, in this embodiment, by spreading water 9 above the new cutting line 8, the cutting torch 6
The machine is submerged in water so that the body can be cut underwater.

このように、本実施例では、容器外側から酸素アセチレ
ンガスを用いて切断を行なうので、さぎの実施例と同じ
効果な奏するとともに、その切断を水中にで行なうよう
にしたので、ヒユーム等の発生が水中で吸収され、雰囲
気中π発生する二次廃棄物の発生量な少なくすることが
できる。
In this way, in this example, cutting is performed using oxygen acetylene gas from the outside of the container, so the same effect as in the rabbit example is achieved, and since the cutting is done underwater, the generation of fume etc. is absorbed in water, and the amount of secondary waste generated in the atmosphere can be reduced.

以上述べたよ5[、本発明では、原子炉圧力容器の外側
から酸素アセチレンガスな用いて切断するよ”)ttt
したので、原子炉圧力容器を信頼性良く、安定して切断
・解体することかで救る。
As stated above, in the present invention, the reactor pressure vessel is cut using oxygen acetylene gas from the outside.
Therefore, the solution is to reliably and stably cut and disassemble the reactor pressure vessel.

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

第1図は原子炉圧力容器の従来の切断・解体方法を示す
原子炉断面図、第2図および第3図は本発明の一実施例
に係る原子炉圧力容器の切断・解体方法な示す原子炉断
面図、第4図は本発明の他の実施例f係る原子炉圧力容
器の切断争解体方法を示す原子炉断面図である。 1・・・・・・原子炉圧力容器、2・・・・・・ステン
レスクラッド、5・・・・・・マニプレータ、6・・・
・・・切断トーチ、8・・・・・・切断予定線。
FIG. 1 is a sectional view of a nuclear reactor showing a conventional method for cutting and dismantling a reactor pressure vessel, and FIGS. 2 and 3 show a method for cutting and disassembling a reactor pressure vessel according to an embodiment of the present invention. FIG. 4 is a sectional view of a nuclear reactor showing a method for cutting and dismantling a reactor pressure vessel according to another embodiment f of the present invention. 1... Reactor pressure vessel, 2... Stainless steel clad, 5... Manipulator, 6...
...Cutting torch, 8... Cutting planned line.

Claims (1)

【特許請求の範囲】[Claims] 1、内面がステンレスクラッドで構成されている原子炉
圧力容器において、遠隔操作されるガス切断トーチで前
記原子炉圧力容器の外側から切断予定線に沿って切断し
て解体を行うことを特徴とする原子炉圧力容器の切断・
解体方法。
1. A nuclear reactor pressure vessel whose inner surface is made of stainless steel cladding is dismantled by cutting along a planned cutting line from the outside of the reactor pressure vessel using a remotely controlled gas cutting torch. Reactor pressure vessel cutting/
Disassembly method.
JP57184465A 1982-10-22 1982-10-22 Method of cutting and dismantling reactor pressure vessel Granted JPS5975199A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57184465A JPS5975199A (en) 1982-10-22 1982-10-22 Method of cutting and dismantling reactor pressure vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57184465A JPS5975199A (en) 1982-10-22 1982-10-22 Method of cutting and dismantling reactor pressure vessel

Publications (2)

Publication Number Publication Date
JPS5975199A true JPS5975199A (en) 1984-04-27
JPH0229200B2 JPH0229200B2 (en) 1990-06-28

Family

ID=16153624

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57184465A Granted JPS5975199A (en) 1982-10-22 1982-10-22 Method of cutting and dismantling reactor pressure vessel

Country Status (1)

Country Link
JP (1) JPS5975199A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014059185A (en) * 2012-09-14 2014-04-03 Mitsubishi Heavy Ind Ltd Reactor vessel lid dismantlement method and disposal method
JP2015031621A (en) * 2013-08-05 2015-02-16 日立Geニュークリア・エナジー株式会社 Apparatus and method for removing top lid of reactor pressure vessel
JP2017021046A (en) * 2016-09-29 2017-01-26 三菱重工業株式会社 Disassembly method and disposal method for reactor vessel lid
JP2017207512A (en) * 2017-08-01 2017-11-24 三菱重工業株式会社 Dismantling method and disposal method of reactor vessel lid

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014059185A (en) * 2012-09-14 2014-04-03 Mitsubishi Heavy Ind Ltd Reactor vessel lid dismantlement method and disposal method
JP2015031621A (en) * 2013-08-05 2015-02-16 日立Geニュークリア・エナジー株式会社 Apparatus and method for removing top lid of reactor pressure vessel
JP2017021046A (en) * 2016-09-29 2017-01-26 三菱重工業株式会社 Disassembly method and disposal method for reactor vessel lid
JP2017207512A (en) * 2017-08-01 2017-11-24 三菱重工業株式会社 Dismantling method and disposal method of reactor vessel lid

Also Published As

Publication number Publication date
JPH0229200B2 (en) 1990-06-28

Similar Documents

Publication Publication Date Title
JPS6318714B2 (en)
EP0145336B1 (en) Method for minimizing the permeation release of tritrium through a nuclear reactor component
JPS5975199A (en) Method of cutting and dismantling reactor pressure vessel
Wang et al. The effect of an applied stress on the welding of irradiated steels
JPH04316000A (en) Method for dismantling nuclear reactor using laser beam
Nixondg et al. A survey of underwater welding techniques
JPH0229199B2 (en)
JPS5570479A (en) Narrow groove co2 gas shielded arc welding method
US20020109003A1 (en) Welding underwater in a chamber with a flux-type backing
JPS62118972A (en) Overhaul method for used atomic reactor pressure container
Bouilly et al. SUPERPHENIX Dismantling-Status and lessons learned
Copus Core-concrete interactions with overlying water pools
JPS62291600A (en) Wet type overhauling method of nuclear reactor facility
JP2810066B2 (en) Repair method of neutron flux monitor housing
Paton et al. Problems of Decommissioning Gas Cooled Reactor Systems
JPS57203756A (en) Preventing method for hydrogen embrittlement of metal and alloy
JPH0447799B2 (en)
JP2001264492A (en) Overpack and its welding method
JPS56168961A (en) Method and device for underwater arc cutting in nuclear reactor
JPH04290998A (en) Underwater thermal cutting method
JPS5564989A (en) Welding method of pipe and pipe plate
JPS5639176A (en) Flush butt welding method
JPS5484610A (en) Sealing method for vessel bottom part liner
JPS53106647A (en) Regenerating method of flux for submerged arc welding
JPS5495952A (en) Repairing method for vertical plane of large cast steel structure by building up