JPS6166999A - Method of overhauling construction of nuclear reactor vessel - Google Patents

Method of overhauling construction of nuclear reactor vessel

Info

Publication number
JPS6166999A
JPS6166999A JP19018084A JP19018084A JPS6166999A JP S6166999 A JPS6166999 A JP S6166999A JP 19018084 A JP19018084 A JP 19018084A JP 19018084 A JP19018084 A JP 19018084A JP S6166999 A JPS6166999 A JP S6166999A
Authority
JP
Japan
Prior art keywords
cutting
reactor vessel
cut
dismantling
water
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.)
Pending
Application number
JP19018084A
Other languages
Japanese (ja)
Inventor
蔦川 雅洋
新堀 邦明
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.)
Toshiba Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
Toshiba Corp
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 Toshiba Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP19018084A priority Critical patent/JPS6166999A/en
Publication of JPS6166999A publication Critical patent/JPS6166999A/en
Pending legal-status Critical Current

Links

Landscapes

  • Working Measures On Existing Buildindgs (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】 〔発明の利用分野〕 本発明は例えば沸騰水■!原子炉(BWR)の原子炉容
器(RPV) 、加圧水型原子炉(PWII)その他の
原子炉の原子炉容器(RV)(以下、これらRPV、R
Vを原子炉容器と総称する)を据付状態から切断撤去す
る原子炉容器の解体工法に関する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention applies to boiling water, for example! Reactor vessel (RPV) of nuclear reactor (BWR), reactor vessel (RV) of pressurized water reactor (PWII) and other nuclear reactors (hereinafter referred to as these RPV, R
This invention relates to a method for dismantling a nuclear reactor vessel by cutting and removing the reactor vessel (V collectively referred to as the reactor vessel) from the installed state.

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

国内外各所に構築された原子ノ〕発雷ブラントは既に稼
働段階に至っており、一定の耐用年限が経過した後のプ
ラント廃棄措置に伴なう解体工法も種々開発されつつあ
る。特に原子炉容器は高放射性廃棄物となり(7るとこ
ろから、小形処理容器への封入可能な大きさまで細分化
することが望ましいと考えられ、据付状態からの解体段
階で成る程度まで切断分離することが検討されている。
Atomic lightning blasting blunts built in various locations in Japan and overseas have already reached the operational stage, and various dismantling methods are being developed for dismantling the plants after a certain useful life has passed. In particular, since the reactor vessel becomes highly radioactive waste (7), it is considered desirable to divide it into small pieces that can be enclosed in small processing vessels, and it is considered desirable to cut and separate the reactor vessel to the extent that it can be disassembled from the installed state. is being considered.

原子力発電プラント運転中は第2図に示すように、原子
炉容器1は炉心2を内包しており、この炉心2からの放
射線の影響を受けて高敢射化している。原子炉容器1の
周囲は原子炉熱遮蔽壁(以下R3Wともいう)3で覆わ
れ、R3Wはベデスクル4Fに設置されている。このR
8W3ににつて炉心2からの敢DJ線が周辺のvi器や
設備、あるいは定期点検時の作業0への悪影響を及ぼす
ことを防11−シている。原子炉容器1を解体する場合
にb、敢a1能汚染範囲の拡大を防11−ηる観点から
R3W3が設置されている状態で原子炉格納容器内で作
業することが望まれる。なお、原子炉容器1には冷却材
循環系統、非常時炉心冷却系統等の種々の配管5が接続
されており、これらの配管5はR8W3の目通孔6に挿
通されている。原子炉容器1の解体部にはこれらの配管
5の切断撤去も必要となる。
As shown in FIG. 2, during the operation of a nuclear power plant, the reactor vessel 1 contains a reactor core 2, and is exposed to high radiation radiation from the reactor core 2. The periphery of the reactor vessel 1 is covered with a reactor heat shielding wall (hereinafter also referred to as R3W) 3, and R3W is installed on the bed desk 4F. This R
Regarding 8W3, the DJ line from the reactor core 2 is prevented from having an adverse effect on surrounding equipment and equipment, or on work during periodic inspections. When dismantling the reactor vessel 1, it is desirable to work inside the reactor containment vessel with R3W3 installed from the viewpoint of preventing the spread of contamination. In addition, various piping 5 such as a coolant circulation system and an emergency core cooling system are connected to the reactor vessel 1, and these piping 5 are inserted into the through hole 6 of R8W3. When dismantling the reactor vessel 1, it is also necessary to cut and remove these pipes 5.

どころで、これまで考えられた原子か容器の解体工法と
しては気中切断と水中切断とがある。気中切断は第3図
に示すJ:うに、切断工具7を例えば原子炉容器1の内
方に挿入し、空気中で切断作業を行なうしので、1!1
に面倒な壓備T稈等を必要どしない。しかしながら、切
断時に発/l iると予想される放射性のじl−ム8や
ドロス、あるいはガス等が飛散し、放射能による汚染範
囲の拡大による環境悪化が懸念され、望ましい対策°と
はいえない。
By the way, the methods of dismantling atoms or containers that have been considered so far include aerial cutting and underwater cutting. In air cutting, the cutting tool 7 is inserted into the inside of the reactor vessel 1 and the cutting operation is performed in the air, as shown in Fig. 3.
There is no need for troublesome T-culms etc. However, although it is a desirable countermeasure, there are concerns about environmental deterioration due to the spread of radioactive smoke, dross, gas, etc. that are expected to be emitted during cutting, and the spread of radioactive contamination. do not have.

一方、水中切断は第4図に示すように、原子炉容器1を
R3Wへの充填水9で水没状態とし、水中に沈めた切I
iT貝10で原子炉容器1を切断するものである。この
水中切断にJ、るど、切1lJi時に発!1−するヒ1
−ムやドロスのほとんどが水中に保持され、環境1’j
染の虞れは生じないと考えられる。
On the other hand, for underwater cutting, as shown in Fig. 4, the reactor vessel 1 is submerged with R3W filling water 9, and the cutter I is submerged in water.
The reactor vessel 1 is cut with an iT shell 10. In this underwater cutting, J, Rudo, Cut at 1lJi! 1-Hi 1
-Most of the dross and dross are retained in the water, and the environment 1'j
It is thought that there is no risk of staining.

ところが、この場合にはR8W3内に水を収容するため
に予備作業として配管類の全てをR3Wの内側で切断撤
去するとともに、R8W3に形成されている配管挿通用
のn通孔6や、ペデスタル4部を水密シール部材11で
月1トηることが必要となる。R8W内部での配管切断
や多数個所のシールには非常に多くの手間、時間がかが
ると予想され、また作業員の被曝防1トの観点からも?
ましくイ1い。
However, in this case, in order to accommodate water in R8W3, all the piping was cut and removed inside R3W as a preliminary work, and the N through hole 6 for piping insertion formed in R8W3 and the pedestal 4 were removed. It is necessary to seal the area with the watertight seal member 11 once a month. It is expected that cutting the pipes and sealing multiple locations inside the R8W will take a great deal of time and effort, and also from the perspective of preventing radiation exposure for workers.
I'm really good.

したがって、これまで知られた解体工法では環境汚染ま
たは作業性の貞から問題があるど考λられる。
Therefore, the demolition methods known so far are considered to have problems in terms of environmental pollution or poor workability.

(発明の目的) 本発明の目的は放射付物質の飛散の虞れがなく、しかも
作業能率がよく、安全性および作業制の両面から最も望
ましい原子炉容器の解体工法を提供することにある。
(Objective of the Invention) An object of the present invention is to provide a method for dismantling a nuclear reactor vessel that is free from the risk of scattering of radioactive materials, has good work efficiency, and is the most desirable from both safety and work system standpoints.

〔発明の概要〕[Summary of the invention]

本発明に係る原子炉容器の解体工法は、原子炉熱遮蔽壁
で囲まれた据付状態にある原子炉容器を上部から順次切
断撤去する工法において、原子炉容器内を水張り状態と
し、切断工程は原子炉容器の内周側から外周側に向って
所定深さまで切込む前切断工程と、この前切断工程で切
残した原子炉容器外周部を完全に切断する後切断工程と
に分けて行ない、前記前切断工程では原子炉容器内水位
を切断線よりも高くして水中切断を施し、前記俊切断T
稈では原子炉容器内水位を切1lyi線よりt)低下さ
りて気中切断を施でことを特徴と4−る。
The reactor vessel dismantling method according to the present invention is a method of sequentially cutting and removing the installed reactor vessel surrounded by the reactor heat shielding wall from the top. The method is divided into a pre-cutting step in which the reactor vessel is cut to a predetermined depth from the inner circumference side toward the outer circumference side, and a post-cutting step in which the outer circumferential portion of the reactor vessel that remains uncut in the pre-cutting step is completely cut. In the pre-cutting step, underwater cutting is performed with the water level in the reactor vessel higher than the cutting line, and the quick cutting T
At the culm, the water level in the reactor vessel is lowered below the 1lyi line and an aerial cut is performed.

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

以下、本発明の一実施例を第1図を参照して説明する。 An embodiment of the present invention will be described below with reference to FIG.

なお、原子炉容器および周辺の配置構成は第2図と共通
であるから、図の同一部分に第2図と同一の符8を使用
して説明する。
Since the arrangement of the reactor vessel and its surroundings is the same as in FIG. 2, the same parts in the figure will be described using the same reference numerals 8 as in FIG. 2.

第1図(a)は前切断工程を示している。即ち、原子炉
容器1内のみを水張りし、R8W3には水張りしない。
FIG. 1(a) shows the pre-cutting step. That is, only the inside of the reactor vessel 1 is filled with water, but R8W3 is not filled with water.

このことから、R8W3のn通孔6やペデスタル4部は
水密シールする必要がない。
From this, it is not necessary to seal the N through hole 6 and the pedestal 4 of R8W3 watertight.

r¥備作業としては、R3W3の外側で配管5を切断す
るとどもに、その切断部のみを水密シール部012で封
止する。原子炉容器1への収容水13の水位は所要切断
線14よりも高くする。イして、原子炉容器1内へ水没
状態で切断工具15を挿入し、原子炉容器1の内周側か
ら外周側に向って所定深さまで切込む。なお、この場合
の切断■貝15はアーク切断工具とし、アーク切断を施
す。
As for the preparation work, the piping 5 is cut outside R3W3, and only the cut portion is sealed with the watertight seal part 012. The water level of the water 13 contained in the reactor vessel 1 is set higher than the required cutting line 14. Then, the cutting tool 15 is inserted into the reactor vessel 1 in a submerged state, and cuts from the inner circumferential side of the reactor vessel 1 toward the outer circumferential side to a predetermined depth. Note that in this case, the cutting shell 15 is an arc cutting tool, and arc cutting is performed.

このアーク切断によれば、例えば1,100MWe級の
原子力発電プラントで使用する肉η11)0#ll++
以上の原子炉容器でも十分に切断部ることができる。も
つとも、肉厚が小さい原子炉容器の場合にはカッター等
の機械切断やガス切断を使用することも可能である。
According to this arc cutting, for example, meat used in a 1,100 MWe class nuclear power plant η11)0#ll++
Even the reactor vessel described above can be sufficiently cut. However, in the case of a reactor vessel with a small wall thickness, it is also possible to use mechanical cutting such as a cutter or gas cutting.

この前切断T稈では原子炉容器1を完全に切断Uず、機
械的切断可能な肉厚を外周側に残存さける切込み途中の
段階で切断作業を中止する。これにより、切断時に発!
1−するヒコームやドロスあるいはnスは収容水13内
に取込まれ、周囲に飛散することがない。
In this pre-cutting T culm, the reactor vessel 1 is not completely cut, but the cutting operation is stopped in the middle of the cut to avoid leaving a wall thickness that can be mechanically cut on the outer circumferential side. This will cause it to emit when disconnected!
1- Hiccomb, dross, or sulfur are taken into the contained water 13 and are not scattered around.

所要切断後は、第1図(b)に示すように、原子炉容器
1内の収容水13の水位を下げ、第1図(C)に示すよ
うに、水位が切断線14よりも低くなったところで水位
低下を止める。なお、水位低下の段階で、水位上方に配
置する配管類は切断撤去する。その((、(り明所工程
に移行する。
After the required cutting, the water level of the contained water 13 in the reactor vessel 1 is lowered, as shown in FIG. 1(b), and the water level is lower than the cutting line 14, as shown in FIG. 1(C). Stop the water level drop at a certain point. Furthermore, when the water level is falling, piping placed above the water level will be cut and removed. The ((, (transition to the clear stage process.

第1図(C)が後切断工程を示している。この工程では
、カッター等の機械的切断■貝16を原子炉容器1内に
挿入し、収容水13の水位上方に露出している切断線1
/Iに沿い、前切断■稈で切残した原子炉容器1の外周
部を機械切断により、完全に切断1−る。なお、図示し
ないが、完全切断口)に切断部分が落下しないように、
吊下具等によって切断部分の支持を行なう。この後切I
Wi11稈では切込mが少Mであり、しかも機械切断で
あることからヒ1−ム等の飛散は少ない。また、収容水
13の水位が切断線14J:りも低いので、切11i峙
に収容水13が溢出する虞れもない。切断後は、切断部
分を撤去し、図示しないプール等に収容する。
FIG. 1(C) shows the post-cutting process. In this step, the shell 16 is mechanically cut using a cutter, etc., and the cut line 1 exposed above the water level of the contained water 13 is inserted into the reactor vessel 1.
The outer periphery of the reactor vessel 1, which was left uncut by the culm from the previous cut, is completely cut 1- along the /I by mechanical cutting. Although not shown, to prevent the cut part from falling into the complete cut opening),
Support the cut part using hanging tools, etc. After this I
In the Wi11 culm, the cutting depth m is small, and since the cutting is done mechanically, there is little scattering of the hem etc. Furthermore, since the water level of the accommodated water 13 is lower than the cut line 14J, there is no risk of the accommodated water 13 overflowing across the cut line 11i. After cutting, the cut portion is removed and stored in a pool (not shown) or the like.

イの後、第1図(d)に示すように、収容水13内に再
びアーク切断工具15を導入し、第1図<8>と同様に
次段階にお+jる前切断T稈に移り、以後前記同様の後
切断工程との組合せによる解体サイクルを繰返す。
After that, as shown in FIG. 1(d), the arc cutting tool 15 is reintroduced into the contained water 13, and the process proceeds to the next stage of pre-cutting T culm in the same manner as in FIG. 1 <8>. Thereafter, the dismantling cycle in combination with the same post-cutting process as described above is repeated.

このようイi原子炉容器の解体工法によれば、従来考え
られた水中切断に法と責なり、原子炉容器1のみを水張
りし、R8Wは水張りしないので、原子炉容器1に接続
される配管5等をR8W3の内側で切断する予備作業が
不要となり、またR8W3のQ通孔6やペデスタル4部
の止栓も必要がない。したがって、これらに係る作業労
力が省略でき、被曝量の低減も同時に図れる。配管類の
切断はR3W3の外側で原子炉容器1の切断と同時期に
行なえ、その作業軽減も図れる。
According to this method of dismantling the reactor vessel, the conventional method of underwater cutting is prohibited, and only the reactor vessel 1 is filled with water, R8W is not filled with water, so the pipes connected to the reactor vessel 1 are There is no need to perform preliminary work such as cutting 5 etc. inside the R8W3, and there is no need to stop the Q through hole 6 or the pedestal 4 of the R8W3. Therefore, the labor involved in these tasks can be omitted, and the amount of radiation exposure can be reduced at the same time. The piping can be cut outside R3W3 at the same time as the reactor vessel 1, and the work can be reduced.

また、ヒコーム、ドロス等が多聞に発生するアーク切断
は水中切断状態で行なうので飛散がなく、一方気中切所
時はそれらの発生が少ない機械切断を行なうので、放射
能の汚染範囲の拡大防止が図れ、環境安全性保持に有効
なものとなる。
In addition, arc cutting, which generates a lot of hichomes and dross, is done underwater, so there is no scattering.Mechanical cutting, on the other hand, generates less of these when cutting in the air, which prevents the spread of radioactive contamination. This will be effective in maintaining environmental safety.

(発明の効果) 以上のように、本発明に係る原子炉容器の解体工法は、
原子炉容器内のみに水張りして、その水位を変化させつ
つ、水中切断による前切断工程ど気中切断による後切断
工程とを組合せ、放射性物質の飛散防止と、面倒な止水
準備作業の省略とを図り、切断作業自体も能率よく行な
えるものである。
(Effects of the invention) As described above, the reactor vessel dismantling method according to the present invention is as follows:
Filling only the inside of the reactor vessel with water and changing the water level, combining the pre-cutting process with underwater cutting and the post-cutting process with aerial cutting, prevents the scattering of radioactive materials and eliminates the troublesome preparation work for water shutoff. With this in mind, the cutting operation itself can be carried out efficiently.

したがって被曝防止による安全性確保と作業性向上とい
う両面、からの要望を満たし、原子炉設備の廃棄Ij1
買に11に対処しくりる効果を奏する。
Therefore, it satisfies both the demands of ensuring safety through radiation exposure prevention and improving work efficiency, and the disposal of nuclear reactor equipment Ij1
It has the effect of dealing with 11 problems.

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

第1図(a)〜(d)は本発明の一実施例を示す■稈説
明図、第2図は原子炉容器おJ:び周辺設備を示す配同
構成図、第3図および第4図はぞれぞれ貸なる従来例を
示す作用説明図である。 1・・・原子炉容器、3・・・原子炉遮蔽壁、15.1
6・・・切断工具、13・・・収容水。 出願人代理人  波 多 野   久 −1〇 −
Figures 1 (a) to (d) are explanatory diagrams showing one embodiment of the present invention; Figure 2 is a layout diagram showing the reactor vessel and peripheral equipment; Figures 3 and 4; Each of the figures is an explanatory view of the operation showing a conventional example. 1... Reactor vessel, 3... Reactor shielding wall, 15.1
6... Cutting tool, 13... Accommodated water. Applicant's agent Hisashi Hatano -10 -

Claims (1)

【特許請求の範囲】 1、原子炉熱遮蔽壁で囲まれた据付状態にある原子炉容
器を上部から順次切断撤去する原子炉容器の解体工法に
おいて、原子炉容器内を水張り状態とし、切断工程は原
子炉容器の内周側から外周側に向つて所定深さまで切込
む前切断工程と、この前切断工程で切残した原子炉容器
外周部を完全に切断する後切断工程とに分けて行ない、
前記前切断工程では原子炉容器内水位を切断線よりも高
くして水中切断を施し、前記後切断工程では原子炉容器
内水位を切断線よりも低下させて気中切断を施すことを
特徴とする原子炉容器の解体工法。 2、前切断工程における水中切断ではアーク切断を使用
する特許請求の範囲第1項記載の原子炉容器の解体工法
。 3、後切断工程における気中切断では機械切断を使用す
る特許請求の範囲第1項記載の原子炉容器の解体工法。
[Scope of Claims] 1. In a method for dismantling a nuclear reactor vessel in which the installed reactor vessel surrounded by a reactor heat shield wall is sequentially cut and removed from the top, the inside of the reactor vessel is filled with water, and the cutting step This process is divided into a pre-cutting process in which the reactor vessel is cut from the inner circumference to the outer circumference to a predetermined depth, and a post-cutting process in which the outer circumference of the reactor vessel that is left uncut in the pre-cutting process is completely cut. ,
In the pre-cutting step, the water level in the reactor vessel is made higher than the cutting line to perform underwater cutting, and in the post-cutting step, the water level in the reactor vessel is lowered than the cutting line to perform aerial cutting. A method for dismantling nuclear reactor vessels. 2. The method for dismantling a nuclear reactor vessel according to claim 1, wherein arc cutting is used in the underwater cutting in the pre-cutting step. 3. The method for dismantling a nuclear reactor vessel according to claim 1, wherein mechanical cutting is used in the aerial cutting in the post-cutting process.
JP19018084A 1984-09-11 1984-09-11 Method of overhauling construction of nuclear reactor vessel Pending JPS6166999A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP19018084A JPS6166999A (en) 1984-09-11 1984-09-11 Method of overhauling construction of nuclear reactor vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP19018084A JPS6166999A (en) 1984-09-11 1984-09-11 Method of overhauling construction of nuclear reactor vessel

Publications (1)

Publication Number Publication Date
JPS6166999A true JPS6166999A (en) 1986-04-05

Family

ID=16253776

Family Applications (1)

Application Number Title Priority Date Filing Date
JP19018084A Pending JPS6166999A (en) 1984-09-11 1984-09-11 Method of overhauling construction of nuclear reactor vessel

Country Status (1)

Country Link
JP (1) JPS6166999A (en)

Similar Documents

Publication Publication Date Title
JPS6166999A (en) Method of overhauling construction of nuclear reactor vessel
US20100004498A1 (en) Reducing the profile of neutron-activated 60Co and removing in layers at the primary system of a permanently shut down nuclear power plant in order to accelerate its dismantling
KR102071568B1 (en) Method for decommissioning nuclear facilities
JP2013205127A (en) Nuclear fuel material cutting device and cutting method in nuclear plant
KR102071567B1 (en) Method for decommissioning nuclear facilities
Demeulemeester et al. The dismantling of the vessel from the Belgian BR3 PWR test reactor
Large Decommissioning of nuclear reactor systems
KR102092373B1 (en) Method for decommissioning nuclear facilities
JPS63115091A (en) Building with radioactive facility part
Steiner et al. Experience with the dismantling of three secondary steam generators in unit A in Gundremmingen by the ‘ice-sawing’technique
Bouilly et al. SUPERPHENIX Dismantling-Status and lessons learned
Jensen Polymer Solidification and Stabilization: Adaptable Processes for Atypical Wastes
Thierfeldt Decommissioning and Waste Management
Chung et al. Adsorptive Removal of Cs-137 and Sr-90 from Water in the Spent Fuel Pool of Taiwan Research Reactor-18169
KR20230145660A (en) Underwater dismantling method of heavy water reactor type nuclear power plant
Weber et al. NEA support to Fukushima Daiichi decommissioning strategy planning
Huber Robotic Underwater Decontamination Services for Nuclear Applications-18464
Mitchell et al. Individual plant examination program-summary and status
KR20230145659A (en) Dismantling method of heavy water type nuclear reactor
Davis Elk River Reactor dismantling
Noynaert et al. The Involvement of SCK• CEN in Decommissioning Projects
Dadoumont et al. Dismantling of the BR3 Reactor Pressure Vessel
Knief Nuclear criticality safety for the TMI-2 recovery program.
Sivintsev The seabed sources of radionuclides in the dumped reactor compartment of the atomic icebreaker,‘Lenin’
Ølgaard Worldwide overview of nuclear submarine decommissioning plans and issues