JP3595416B2 - Reactor pressure vessel unloading method - Google Patents

Reactor pressure vessel unloading method Download PDF

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Publication number
JP3595416B2
JP3595416B2 JP19479696A JP19479696A JP3595416B2 JP 3595416 B2 JP3595416 B2 JP 3595416B2 JP 19479696 A JP19479696 A JP 19479696A JP 19479696 A JP19479696 A JP 19479696A JP 3595416 B2 JP3595416 B2 JP 3595416B2
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Japan
Prior art keywords
pressure vessel
reactor
reactor pressure
injection amount
water injection
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JPH1039077A (en
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博美 藤澤
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Toshiba Corp
Tokyo Electric Power Co Inc
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Toshiba Corp
Tokyo Electric Power Co Inc
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    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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Description

【０００１】
【発明の属する技術分野】
本発明は、原子炉圧力容器搬出方法に関するものである。より詳しくは、短時間のうちに施設に影響を与えることなく原子炉圧力容器を交換し得るようにした原子炉圧力容器搬出方法に関するものである。
【０００２】
【従来の技術】
原子力発電施設は、予め耐用年数を決めて設計されており、所定の耐用年数が経過すると、施設は破棄されることになる。
【０００３】
しかし、原子力発電施設は、実際には、決められた耐用年数に対して十分な余裕を持っているので、寿命の尽きた部品のみを交換することにより、原子力発電施設の延命を図ることが可能である。
【０００４】
そのため、寿命の尽きた部品を交換する技術を確立する必要があるが、この場合の交換すべき部品の代表的なものとしては、原子炉圧力容器などが挙げられる。
【０００５】
しかるに、現在のところ、原子炉圧力容器を交換した実例はまだ存在せず、交換技術は確立されていない。
【０００６】
【発明が解決しようとする課題】
寿命の尽きた原子炉圧力容器を原子力発電施設から搬出する場合、放射化した原子炉圧力容器をいかに遮蔽し、いかに短時間に、施設に影響を与えずに外部へ搬出するかが重要になる。
【０００７】
本発明は、上述の実情に鑑み、短時間のうちに施設に影響を与えることなく原子炉圧力容器を交換し得るようにした原子炉圧力容器搬出方法を提供することを目的とするものである。
【０００８】
【課題を解決するための手段】
上記目的を達成するため、請求項１に記載の発明は、原子炉格納容器１から搬出すべき原子炉圧力容器４の内部に注水量低減部材２４，２６，３０，３１を、圧力容器本体１３の全方向に対して間隔が保たれるように配置し、次いで、圧力容器本体１３の内部に遮蔽用水２８を注入して満水状態とし、原子炉格納容器１の内部で圧力容器本体１３の外周を包囲している原子炉遮蔽壁６の上部と原子炉圧力容器４を一体的に引き上げて原子炉格納容器１の外部へ搬出する。
【０００９】
請求項２に記載の発明は、注水量低減部材に空気タンク２４，２６を用いる。
【００１０】
請求項３に記載の発明は、注水量低減部材に発泡樹脂３０，３１を用いる。
【００１１】
請求項４に記載の発明は、原子炉遮蔽壁６を下部ノズル開口部８の下辺位置イで切断し、原子炉遮蔽壁６の上部と原子炉圧力容器４を一体的に引き上げる。
【００１２】
原子炉格納容器１から原子炉圧力容器４を取り出す場合、原子炉遮蔽壁６を下部ノズル開口部８の下辺位置イで切断する。
【００１３】
そして、圧力容器本体１３の内部に空気タンク２４，２６や発泡樹脂３０，３１などの注水量低減部材を挿入配置する。
【００１４】
このようにして空気タンク２４，２６などがセットされたら、圧力容器本体１３の内部に遮蔽用水２８を注入し、圧力容器本体１３内部を満水状態とする。
【００１５】
こうして準備ができたら、クレーンなどを用いて、圧力容器本体１３を引き上げ、原子炉遮蔽壁６の上部ごと圧力容器本体１３を外部へ搬出する。
【００１６】
このように、圧力容器本体１３内部に遮蔽用水２８を注入して、遮蔽用水２８で遮蔽させるようにしているので、簡単且つ確実に遮蔽を行わせることができる。
【００１７】
又、圧力容器本体１３内部に空気タンク２４，２６などを挿入した状態で、遮蔽用水２８を注入するようにしているので、最小限の遮蔽用水２８で遮蔽させることができ、吊上げ重量を軽減させることが可能となる。
【００１８】
更に、原子炉遮蔽壁６の上部ごと圧力容器本体１３を外部へ搬出させるようにしているので、工程を省略することができる。
【００１９】
以上により、短時間のうちに施設に影響を与えることなく原子炉圧力容器４を交換することが可能となる。
【００２０】
特に、注水量低減部材として、発泡樹脂３０，３１を使用することにより、空気タンク２４，２６に比べて搬出時の吊上げ重量を大幅に低減することができるようになると共に、注水量低減部材の据え付けの手間や、搬出作業の手間の低減を図ることが可能となる。
【００２１】
【発明の実施の形態】
以下、本発明の実施の形態を、図示例と共に説明する。
【００２２】
図１〜図４は、本発明の第一の実施の形態である。
【００２３】
図中、１は原子炉格納容器、２は原子炉格納容器１上部の建屋部、３は原子炉格納容器１下部のドライウエル部、４は原子炉格納容器１内部に収容される原子炉圧力容器、５はドライウエル部３に設けられた、原子炉圧力容器４の下部を支持するためのペデスタル、６はペデスタル５に下部を支持されて、原子炉圧力容器４の外周を包囲するよう設けられた原子炉遮蔽壁、７は原子炉遮蔽壁６の上部に周方向複数箇所形成された上部ノズル開口部、８は原子炉遮蔽壁６の下部に周方向複数箇所形成された下部ノズル開口部、９は原子炉圧力容器４の上部を図示しないベローズを介して原子炉格納容器１に接続するためのバルクヘッド部である。
【００２４】
そして、上記原子炉圧力容器４は、下部に制御棒を出し入れするためのＣＲＤハウジング１０を有し、前記上部ノズル開口部７や下部ノズル開口部８に対応する側部にそれぞれ上部ノズル１１や下部ノズル１２を有する圧力容器本体１３と、複数のノズル１４を有する蓋体１５と、圧力容器本体１３と蓋体１５とを締結するスタットボルト１６とで構成されている。
【００２５】
又、圧力容器本体１３内の下部には、シュラウド１７と呼ばれる筒状体が取り付けられており、シュラウド１７の上部に取り付けられた上部格子板１８と中間部に取り付けられた炉心支持板１９との間に炉心域２０が形成されている。
【００２６】
尚、図中、２１，２２は上部ノズル開口部７や下部ノズル開口部８をそれぞれ閉止するための開口閉止板、２３は圧力容器本体１３と原子炉遮蔽壁６上部とを固定する固定ボルト、図２中、２４は圧力容器本体１３の上部空間２５に挿入された上部空気タンク（注水量低減部材）、２６は圧力容器本体１３の炉心域２０に挿入された下部空気タンク（注水量低減部材）、２７は圧力容器本体１３やシュラウド１７と上部空気タンク２４や下部空気タンク２６との間に介装されるターンバックル式などの位置調整支持部材、２８は圧力容器本体１３内部に注入される遮蔽用水、図４中、２９は蓋体１５部分に取り付けて図示しないクレーンで圧力容器本体１３を吊り上げるための吊部材である。
【００２７】
原子炉格納容器１から原子炉圧力容器４を取り出す場合、原子炉圧力容器４に取り付けられた上部ノズル１１や下部ノズル１２やＣＲＤハウジング１０と、外部の機器類との縁を切り、上部ノズル１１や下部ノズル１２やＣＲＤハウジング１０の開口部を閉止し、上部ノズル開口部７や下部ノズル開口部８をそれぞれ開口閉止板２１，２２で閉止すると共に、図３に破線イで示すように、原子炉遮蔽壁６を下部ノズル開口部８の下辺位置で切断する。
【００２８】
上記作業と並行させて、原子炉圧力容器４からスタットボルト１６を外して蓋体１５を開け、圧力容器本体１３の内部を分解して、原子炉圧力容器４と同時に撤去する部品以外の部品類を撤去する。
【００２９】
以上の作業が済んだら、圧力容器本体１３の炉心域２０に下部空気タンク２６を挿入配置し、下部空気タンク２６とシュラウド１７の間に位置調整支持部材２７を介装して、下部空気タンク２６をシュラウド１７に固定させると共に、位置調整支持部材２７を調整して、両者の間隔が、全方向に対し、水による遮蔽に必要な最低限の間隔と同じかより以上の間隔となるように保持させる。
【００３０】
同様に、圧力容器本体１３の上部空間２５に上部空気タンク２４を挿入配置し、上部空気タンク２４と圧力容器本体１３の間に位置調整支持部材２７を介装して、上部空気タンク２４を圧力容器本体１３に固定させると共に、位置調整支持部材２７を調整して、両者の間隔が、全方向に対し、水による遮蔽に必要な最低限の間隔と同じかより以上の間隔となるように保持させる。
【００３１】
このようにして下部空気タンク２６と上部空気タンク２４がセットされたら、再び圧力容器本体１３に蓋体１５を取り付け、更に、蓋体１５部分に吊部材２９を取り付けて、蓋体１５に形成したノズル１４から、圧力容器本体１３の内部に遮蔽用水２８を注入し、圧力容器本体１３内部を満水状態とする。
【００３２】
こうして準備ができたら、図４に示すように、図示しないクレーンなどを用いて、吊部材２９を介して圧力容器本体１３を引き上げ、原子炉遮蔽壁６の上部ごと圧力容器本体１３を外部へ搬出する。
【００３３】
このように、本実施の形態によれば、圧力容器本体１３内部に遮蔽用水２８を注入して、遮蔽用水２８で遮蔽させるようにしているので、簡単且つ確実に遮蔽を行わせることができる。
【００３４】
又、圧力容器本体１３内部に下部空気タンク２６や上部空気タンク２４を挿入した状態で、遮蔽用水２８を注入するようにしているので、最小限の遮蔽用水２８で遮蔽させることができ、吊上げ重量を軽減させることが可能となる。
【００３５】
更に、原子炉遮蔽壁６の上部ごと圧力容器本体１３を外部へ搬出させるようにしているので、工程を省略することができる。
【００３６】
以上により、短時間のうちに施設に影響を与えることなく原子炉圧力容器４を交換することが可能となる。
【００３７】
図５は、本発明の第二の実施の形態であり、注水量低減部材として、上部空気タンク２４や下部空気タンク２６に替えて、発泡ウレタンフォームなどの発泡樹脂３０，３１を使用するようにした、原子炉圧力容器４の搬出方法にかかるものである。
【００３８】
より詳しくは、原子炉圧力容器４から蓋体１５を開け、圧力容器本体１３の内部を分解して、原子炉圧力容器４と同時に撤去する部品以外の部品類を除去した後、圧力容器本体１３の炉心域２０に所要の形状に膨らませられるようにしたビニール袋３２を挿入配置し、ビニール袋３２に発泡樹脂３１の原液と発泡材を注入して発泡させるようにする。
【００３９】
同様に、圧力容器本体１３の上部空間２５に所要の形状に膨らませられるようにしたビニール袋３３を挿入配置し、ビニール袋３３に発泡樹脂３０の原液と発泡材を注入して発泡させるようにする。
【００４０】
こうして形成された発泡樹脂３０，３１は、位置調整支持部材２７を用いて、全方向に対し、水による遮蔽に必要な最低限の間隔と同じかより以上の間隔となるよう、シュラウド１７や圧力容器本体１３にビニール袋３２，３３部分を保持させるようにする。
【００４１】
このように、注水量低減部材として、発泡ウレタンフォームなどの発泡樹脂３０，３１を使用することにより、上部空気タンク２４や下部空気タンク２６に比べて搬出時の吊上げ重量を大幅に低減することができるようになると共に、注水量低減部材の据え付けの手間や、搬出作業の手間の低減を図ることが可能となる。
【００４２】
尚、ビニール袋３２，３３への原液と発泡材との注入は、蓋体１５を開けた状態で行っても、蓋体１５を閉じた状態で、ノズル１４を通して行っても良い。
【００４３】
上記以外については、前記実施の形態と同様の構成を備えており、同様の作用・効果を得ることができる。
【００４４】
尚、本発明は、上述の実施の形態にのみ限定されるものではなく、本発明の要旨を逸脱しない範囲内において種々変更を加え得ることは勿論である。
【００４５】
【発明の効果】
以上説明したように、本発明の原子炉圧力容器搬出方法によれば、短時間のうちに施設に影響を与えることなく原子炉圧力容器を交換することができるという優れた効果を奏し得る。
【図面の簡単な説明】
【図１】本発明の第一の実施の形態の全体概略側方断面図である。
【図２】原子炉圧力容器内部に空気タンクを挿入配置した状態を示す全体概略側方断面図である。
【図３】原子炉遮蔽壁の部分的な展開図である。
【図４】原子炉圧力容器を原子炉遮蔽壁の上部と一体的に搬出する状態を示す全体概略側方断面図である。
【図５】本発明の第二の実施の形態の全体概略側方断面図である。
【符号の説明】
１ 原子炉格納容器
４ 原子炉圧力容器
６ 原子炉遮蔽壁
８ 下部ノズル開口部
２４，２６ 空気タンク（上部空気タンク、下部空気タンク、注水量低減部材）
２８ 遮蔽用水
３０，３１ 発泡樹脂（注水量低減部材）
イ 下辺位置[0001]
TECHNICAL FIELD OF THE INVENTION
The present invention relates to a method for unloading a reactor pressure vessel. More specifically, the present invention relates to a reactor pressure vessel unloading method capable of replacing a reactor pressure vessel without affecting a facility in a short time.
[0002]
[Prior art]
Nuclear power generation facilities are designed with their service lives determined in advance, and after a predetermined service life has elapsed, the facilities will be destroyed.
[0003]
However, nuclear power facilities actually have sufficient margin for the specified service life, so it is possible to extend the life of nuclear power facilities by replacing only parts whose life has expired. It is.
[0004]
For this reason, it is necessary to establish a technology for replacing a component whose service life has expired. In this case, a typical example of a component to be replaced is a reactor pressure vessel.
[0005]
However, at present, there is no actual case of replacing the reactor pressure vessel, and no replacement technology has been established.
[0006]
[Problems to be solved by the invention]
When transporting an expired reactor pressure vessel from a nuclear power generation facility, it is important how to shield the activated reactor pressure vessel and how quickly it can be transported outside without affecting the facility. .
[0007]
The present invention has been made in view of the above circumstances, and has as its object to provide a reactor pressure vessel unloading method capable of replacing a reactor pressure vessel without affecting a facility in a short time. .
[0008]
[Means for Solving the Problems]
In order to achieve the above object, the invention according to claim 1 is characterized in that the water injection amount reducing members 24, 26, 30, 31 are provided inside the reactor pressure vessel 4 to be carried out of the reactor containment vessel 1, and the pressure vessel main body 13. Are arranged so as to be spaced from each other in all directions, and then the shielding water 28 is injected into the pressure vessel main body 13 to make it full, and the outer periphery of the pressure vessel main body 13 inside the reactor containment vessel 1 The upper part of the reactor shield wall 6 surrounding the reactor and the reactor pressure vessel 4 are integrally pulled up and carried out of the containment vessel 1.
[0009]
The invention according to claim 2 uses the air tanks 24 and 26 for the water injection amount reducing member.
[0010]
According to a third aspect of the present invention, foamed resins 30 and 31 are used for the water injection amount reducing member.
[0011]
According to a fourth aspect of the present invention, the reactor shield wall 6 is cut at the lower side position A of the lower nozzle opening 8, and the upper part of the reactor shield wall 6 and the reactor pressure vessel 4 are integrally pulled up.
[0012]
When removing the reactor pressure vessel 4 from the reactor containment vessel 1, the reactor shield wall 6 is cut at the lower side position a of the lower nozzle opening 8.
[0013]
Then, a water injection amount reducing member such as the air tanks 24 and 26 and the foamed resins 30 and 31 is inserted and arranged inside the pressure vessel body 13.
[0014]
When the air tanks 24, 26 and the like are set in this manner, the shielding water 28 is injected into the pressure vessel main body 13, and the pressure vessel main body 13 is filled with water.
[0015]
When the preparation is completed, the pressure vessel main body 13 is pulled up using a crane or the like, and the pressure vessel main body 13 together with the upper portion of the reactor shield wall 6 is carried out.
[0016]
As described above, since the shielding water 28 is injected into the inside of the pressure vessel main body 13 and is shielded by the shielding water 28, the shielding can be performed easily and reliably.
[0017]
Further, since the shielding water 28 is injected in a state where the air tanks 24, 26 and the like are inserted into the pressure vessel main body 13, the shielding water 28 can be shielded with the minimum shielding water 28, and the lifting weight can be reduced. It becomes possible.
[0018]
Furthermore, since the pressure vessel main body 13 is carried out to the outside together with the upper part of the reactor shield wall 6, the process can be omitted.
[0019]
As described above, it is possible to replace the reactor pressure vessel 4 in a short time without affecting the facility.
[0020]
In particular, by using the foamed resin 30, 31 as the water injection amount reducing member, the lifting weight at the time of carrying out can be greatly reduced as compared with the air tanks 24, 26, and the water injection amount reducing member can be used. It is possible to reduce the labor of installation and the labor of unloading work.
[0021]
BEST MODE FOR CARRYING OUT THE INVENTION
Hereinafter, embodiments of the present invention will be described with reference to the drawings.
[0022]
1 to 4 show a first embodiment of the present invention.
[0023]
In the drawing, reference numeral 1 denotes a reactor containment vessel, 2 denotes a building section above the reactor containment vessel 1, 3 denotes a dry well section below the reactor containment vessel 1, and 4 denotes a reactor pressure contained in the reactor containment vessel 1. Vessel 5 is a pedestal provided in drywell section 3 for supporting the lower part of reactor pressure vessel 4, and 6 is supported on pedestal 5 at the lower part and surrounds the outer periphery of reactor pressure vessel 4. The reactor shield wall provided, 7 is an upper nozzle opening formed at a plurality of locations in the circumferential direction above the reactor shield wall 6, and 8 is a lower nozzle opening formed at a plurality of locations in the circumferential direction below the reactor shield wall 6. Numeral 9 denotes a bulkhead for connecting the upper part of the reactor pressure vessel 4 to the reactor containment vessel 1 via a bellows (not shown).
[0024]
The reactor pressure vessel 4 has a CRD housing 10 at a lower portion for inserting and removing a control rod, and an upper nozzle 11 and a lower portion at side portions corresponding to the upper nozzle opening 7 and the lower nozzle opening 8, respectively. It comprises a pressure vessel main body 13 having a nozzle 12, a lid 15 having a plurality of nozzles 14, and a stat bolt 16 for fastening the pressure vessel main body 13 and the lid 15.
[0025]
A cylindrical body called a shroud 17 is attached to a lower part in the pressure vessel body 13, and an upper lattice plate 18 attached to an upper part of the shroud 17 and a core support plate 19 attached to an intermediate part. A core region 20 is formed therebetween.
[0026]
In the drawings, reference numerals 21 and 22 denote opening closing plates for closing the upper nozzle opening 7 and the lower nozzle opening 8, respectively, fixing bolts 23 for fixing the pressure vessel main body 13 and the upper part of the reactor shielding wall 6, In FIG. 2, reference numeral 24 denotes an upper air tank (water injection amount reducing member) inserted into an upper space 25 of the pressure vessel main body 13, and reference numeral 26 denotes a lower air tank (water injection amount reducing member) inserted into a core region 20 of the pressure container main body 13. ) And 27 are position adjustment support members of a turnbuckle type or the like interposed between the pressure vessel body 13 or the shroud 17 and the upper air tank 24 or the lower air tank 26, and 28 is injected into the pressure vessel body 13. In FIG. 4, reference numeral 29 denotes a shielding member attached to the cover 15 for lifting the pressure vessel main body 13 with a crane (not shown).
[0027]
When taking out the reactor pressure vessel 4 from the reactor containment vessel 1, the upper nozzle 11, the lower nozzle 12, the CRD housing 10 attached to the reactor pressure vessel 4 and the external equipment are cut off, and the upper nozzle 11 is removed. And the lower nozzle 12 and the opening of the CRD housing 10 are closed, and the upper nozzle opening 7 and the lower nozzle opening 8 are closed by opening closing plates 21 and 22, respectively, as shown in FIG. The furnace shielding wall 6 is cut at the lower side of the lower nozzle opening 8.
[0028]
In parallel with the above operation, the stat bolt 16 is removed from the reactor pressure vessel 4, the lid 15 is opened, the inside of the pressure vessel body 13 is disassembled, and parts other than the parts to be removed simultaneously with the reactor pressure vessel 4 To remove.
[0029]
When the above operation is completed, the lower air tank 26 is inserted and arranged in the core region 20 of the pressure vessel main body 13, and a position adjusting support member 27 is interposed between the lower air tank 26 and the shroud 17, and the lower air tank 26 is inserted. Is fixed to the shroud 17 and the position adjustment support member 27 is adjusted so that the distance between the two is equal to or greater than the minimum distance required for shielding by water in all directions. Let it.
[0030]
Similarly, the upper air tank 24 is inserted and arranged in the upper space 25 of the pressure vessel main body 13, and a position adjusting support member 27 is interposed between the upper air tank 24 and the pressure vessel main body 13 to pressurize the upper air tank 24. It is fixed to the container body 13 and the position adjustment support member 27 is adjusted so that the distance between the two is equal to or greater than the minimum distance required for shielding by water in all directions. Let it.
[0031]
When the lower air tank 26 and the upper air tank 24 are set in this manner, the lid 15 is attached to the pressure vessel main body 13 again, and the hanging member 29 is attached to the lid 15 to form the lid 15. The shielding water 28 is injected into the pressure vessel main body 13 from the nozzle 14 to make the pressure vessel main body 13 full.
[0032]
When the preparation is completed in this way, as shown in FIG. 4, the pressure vessel main body 13 is pulled up via the hanging member 29 using a crane or the like (not shown), and the pressure vessel main body 13 together with the upper part of the reactor shield wall 6 is taken out. I do.
[0033]
As described above, according to the present embodiment, since the shielding water 28 is injected into the pressure vessel main body 13 and is shielded by the shielding water 28, the shielding can be easily and reliably performed.
[0034]
Further, since the shielding water 28 is injected in a state where the lower air tank 26 and the upper air tank 24 are inserted into the pressure vessel body 13, the shielding water 28 can be shielded with the minimum shielding water 28, and the lifting weight can be increased. Can be reduced.
[0035]
Furthermore, since the pressure vessel main body 13 is carried out to the outside together with the upper part of the reactor shield wall 6, the process can be omitted.
[0036]
As described above, it is possible to replace the reactor pressure vessel 4 in a short time without affecting the facility.
[0037]
FIG. 5 shows a second embodiment of the present invention, in which foamed resin 30, 31 such as urethane foam is used as the water injection amount reducing member instead of the upper air tank 24 and the lower air tank 26. This relates to a method of unloading the reactor pressure vessel 4.
[0038]
More specifically, the lid 15 is opened from the reactor pressure vessel 4, the inside of the pressure vessel body 13 is disassembled, and parts other than the parts to be removed simultaneously with the reactor pressure vessel 4 are removed. A plastic bag 32 that can be inflated into a required shape is inserted and arranged in the core region 20 of the furnace, and the undiluted solution of the foamed resin 31 and the foaming material are injected into the plastic bag 32 to foam.
[0039]
Similarly, a plastic bag 33 adapted to be inflated into a required shape is inserted and arranged in the upper space 25 of the pressure vessel main body 13, and the undiluted solution of the foamed resin 30 and the foam material are injected into the plastic bag 33 and foamed. .
[0040]
The foamed resins 30 and 31 formed in this manner are adjusted by using the position adjusting support member 27 so that the shroud 17 and the pressure are adjusted so as to be equal to or longer than the minimum interval required for shielding by water in all directions. The plastic bags 32 and 33 are held by the container body 13.
[0041]
As described above, by using the foamed resin 30, 31 such as foamed urethane foam as the water injection amount reducing member, it is possible to greatly reduce the lifting weight at the time of carrying out as compared with the upper air tank 24 and the lower air tank 26. In addition to this, it is possible to reduce the labor for installing the water injection amount reducing member and the labor for carrying out the work.
[0042]
The injection of the undiluted solution and the foam material into the plastic bags 32 and 33 may be performed with the lid 15 opened or through the nozzle 14 with the lid 15 closed.
[0043]
Except for the above, it has the same configuration as the above-described embodiment, and can obtain the same operation and effect.
[0044]
It should be noted that the present invention is not limited only to the above-described embodiment, and it goes without saying that various changes can be made without departing from the spirit of the present invention.
[0045]
【The invention's effect】
As described above, according to the reactor pressure vessel unloading method of the present invention, an excellent effect that the reactor pressure vessel can be replaced in a short time without affecting the facility can be obtained.
[Brief description of the drawings]
FIG. 1 is an overall schematic side sectional view of a first embodiment of the present invention.
FIG. 2 is an overall schematic side sectional view showing a state in which an air tank is inserted and arranged inside the reactor pressure vessel.
FIG. 3 is a partial development view of a reactor shield wall.
FIG. 4 is an overall schematic side sectional view showing a state in which the reactor pressure vessel is carried out integrally with an upper portion of a reactor shield wall.
FIG. 5 is an overall schematic side sectional view of a second embodiment of the present invention.
[Explanation of symbols]
DESCRIPTION OF SYMBOLS 1 Reactor containment vessel 4 Reactor pressure vessel 6 Reactor shielding wall 8 Lower nozzle opening 24, 26 Air tank (upper air tank, lower air tank, water injection amount reducing member)
28 Shielding water 30, 31 Foamed resin (material for reducing water injection)
B Lower position

Claims (4)

原子炉格納容器（１）から搬出すべき原子炉圧力容器（４）の内部に注水量低減部材（２４）（２６）（３０）（３１）を、圧力容器本体（１３）の内部に取り付けてあるシュラウド（１７）と注水量低減部材（２６）（３１）との間隔が、また、圧力容器本体（１３）と注水量低減部材（２４）（３０）との間隔が全方向に対し、水による遮蔽に必要な最低限の間隔と同じかより以上の間隔となるように保持させ、次いで、圧力容器本体（１３）の内部に遮蔽用水（２８）を注入して満水状態とし、原子炉格納容器（１）の内部で圧力容器本体（１３）の外周を包囲している原子炉遮蔽壁（６）の上部と原子炉圧力容器（４）を一体的に引き上げて原子炉格納容器（１）の外部へ搬出することを特徴とする原子炉圧力容器搬出方法。The water injection amount reducing members (24), (26), (30), and (31) are mounted inside the pressure vessel body (13) inside the reactor pressure vessel (4) to be carried out of the reactor containment vessel (1). The distance between a certain shroud (17) and the water injection amount reducing members (26) and (31), and the space between the pressure vessel body (13) and the water injection amount reducing members (24) and (30), The pressure is maintained so as to be equal to or longer than the minimum interval required for shielding by the pressure vessel, and then the shielding water (28) is injected into the pressure vessel body (13) to make it full, and the reactor is housed. The upper part of the reactor shield wall (6) surrounding the outer periphery of the pressure vessel main body (13) inside the vessel (1) and the reactor pressure vessel (4) are integrally lifted and the reactor containment vessel (1) A method for unloading a reactor pressure vessel, comprising unloading the reactor pressure vessel. 注水量低減部材が、空気タンク（２４）（２６）である請求項１記載の原子炉圧力容器搬出方法。2. The method according to claim 1, wherein the water injection amount reducing member is an air tank (24) (26). 注水量低減部材が、発泡樹脂（３０）（３１）である請求項１記載の原子炉圧力容器搬出方法。The method for carrying out a reactor pressure vessel according to claim 1, wherein the water injection amount reducing member is a foamed resin (30) (31). 原子炉遮蔽壁（６）を下部ノズル開口部（８）の下辺位置（イ）で切断し、原子炉遮蔽壁（６）の上部と原子炉圧力容器（４）を一体的に引き上げる請求項１記載の原子炉圧力容器搬出方法。The reactor shield wall (6) is cut at a lower side position (a) of the lower nozzle opening (8), and the upper part of the reactor shield wall (6) and the reactor pressure vessel (4) are pulled up integrally. The method for carrying out a reactor pressure vessel described in the above.
JP19479696A 1996-07-24 1996-07-24 Reactor pressure vessel unloading method Expired - Fee Related JP3595416B2 (en)

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JP4177964B2 (en) * 1999-03-31 2008-11-05 日立Ｇｅニュークリア・エナジー株式会社 How to carry out reactor internals
JP4177987B2 (en) 2000-02-25 2008-11-05 日立Ｇｅニュークリア・エナジー株式会社 Reactor vessel handling
JP3786009B2 (en) * 2000-03-13 2006-06-14 株式会社日立製作所 Reactor vessel handling
JP4221177B2 (en) * 2000-03-15 2009-02-12 日立Ｇｅニュークリア・エナジー株式会社 How to handle the equipment
JP3551888B2 (en) 2000-03-31 2004-08-11 株式会社日立製作所 Handling of large structures inside the reactor building
JP2003035792A (en) * 2001-07-19 2003-02-07 Ishikawajima Harima Heavy Ind Co Ltd Reactor renewal construction method for nuclear power facility
US20020176529A1 (en) 2002-05-14 2002-11-28 Hitachi, Ltd. Reactor vessel handling method

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