JP3654716B2 - Reactor pressure vessel removal method - Google Patents

Reactor pressure vessel removal method Download PDF

Info

Publication number
JP3654716B2
JP3654716B2 JP19479596A JP19479596A JP3654716B2 JP 3654716 B2 JP3654716 B2 JP 3654716B2 JP 19479596 A JP19479596 A JP 19479596A JP 19479596 A JP19479596 A JP 19479596A JP 3654716 B2 JP3654716 B2 JP 3654716B2
Authority
JP
Japan
Prior art keywords
pressure vessel
reactor
reactor pressure
shielding
attached
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
JP19479596A
Other languages
Japanese (ja)
Other versions
JPH1039076A (en
Inventor
博美 藤澤
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 Corp
Tokyo Electric Power Co Inc
Original Assignee
Toshiba Corp
Tokyo Electric Power Co Inc
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 Corp, Tokyo Electric Power Co Inc filed Critical Toshiba Corp
Priority to JP19479596A priority Critical patent/JP3654716B2/en
Publication of JPH1039076A publication Critical patent/JPH1039076A/en
Application granted granted Critical
Publication of JP3654716B2 publication Critical patent/JP3654716B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

Classifications

    • 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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

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】
本発明は、原子炉格納容器１から搬出すべき原子炉圧力容器４の内部に遮蔽用水２４を注入して当該圧力容器本体１３の下部にのみ遮蔽用水２４が貯まった状態とし、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の上部に圧力容器本体１３上部の外周部分を覆い得る外面上部遮蔽材２５を載せ、原子炉圧力容器４を引き上げてその外周に外面上部遮蔽材２５を取り付け、原子炉圧力容器４及び外面上部遮蔽材２５を一体的に原子炉格納容器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にかかるものである。
【０００９】
この場合において、原子炉格納容器１の外部へ搬出した圧力容器本体１３を輸送スキッド２８に載置して支持する時に、輸送スキッド２８の上部に取付けた外面下部遮蔽材２９で、圧力容器本体１３下部を覆うようにしても良い。
【００１０】
本発明によれば、以下の作用が得られる。
【００１１】
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、圧力容器本体１３の内部に遮蔽用水２４を注入し、圧力容器本体１３の下部に遮蔽用水２４が貯まった状態とする。
【００１２】
こうして準備ができたら、原子炉圧力容器４を有る程度引き上げ、原子炉圧力容器４の外周に外面上部遮蔽材２５を取付ける。
【００１３】
この際、原子炉圧力容器４下部にまで外面上部遮蔽材２５を取付けるようにすると、作業に時間が掛ってしまうため、圧力容器本体１３の下部は遮蔽用水２４で遮蔽させるようにしている。従って、遮蔽用水２４は、外面上部遮蔽材２５の下端よりも上のレベルまで入れるようにする。
【００１４】
原子炉圧力容器４に外面上部遮蔽材２５が取付けられたら、原子炉圧力容器４の引き上げを再開し、圧力容器本体１３を外部へ搬出して、輸送スキッド２８の上部に載せる。
【００１５】
すると、輸送スキッド２８の上部には外面下部遮蔽材２９が取付けられているので、原子炉圧力容器４下部の遮蔽用水２４で遮蔽されていた部分が外面下部遮蔽材２９で遮蔽されることとなる。
【００１６】
こうして、原子炉圧力容器４全体が遮蔽されたら、原子炉圧力容器４を横倒しにして処分施設へ搬送する。
【００１７】
このように、圧力容器本体１３の下部に遮蔽用水２４を注入して、外面上部遮蔽材２５で覆われていない部分を遮蔽用水２４で遮蔽させるようにしているので、簡単に圧力容器本体１３に外面上部遮蔽材２５を取付けて、確実に遮蔽を行わせることができる。
【００１８】
又、圧力容器本体１３下部にのみ、遮蔽用水２４を注入するようにしているので、遮蔽用水２４が少なくて済み、吊上げ重量を軽減させることが可能となる。
【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】
【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。
【００２１】
図１〜図４は、本発明の実施の形態の一例である。
【００２２】
図中、１は原子炉格納容器、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は原子炉格納容器１の底部に設けられた、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。
【００２３】
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。
【００２４】
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。
【００２５】
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内部に注入される遮蔽用水、２５は圧力容器本体１３上部の外周部分を覆うように取付けられる外面上部遮蔽材、２６はシュラウド１７の上面に取付けられる内面遮蔽材、２７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、図４中、２８は外部へ搬出した圧力容器本体１３を載置して支持するための輸送スキッド、２９は輸送スキッド２８の上部に取付けられた、圧力容器本体１３下部の外周部分を覆うための外面下部遮蔽材である。
【００２６】
次に、作動について説明する。
【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と下部ノズル１２は、原子炉遮蔽壁６と緩衝する部分を切断する。
【００２８】
そして、切断された上部ノズル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、必要に応じて、それぞれ開口閉止板２１，２２で閉止する。
【００２９】
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し、シュラウド１７の上面に内面遮蔽材２６を取付ける。
【００３０】
こうしてシュラウド１７の上面に内面遮蔽材２６が取付けられたら、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２７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２４を注入し、圧力容器本体１３の下部に遮蔽用水２４が貯まった状態とする。
【００３１】
こうして準備ができたら、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２３を外し、原子炉遮蔽壁６上部に、周方向に対し複数に分割した状態の外面上部遮蔽材２５を載せて、図２に示すように、図示しないクレーンなどを用いて、吊部材２７を介して原子炉圧力容器４を引き上げる。
【００３２】
そして、原子炉圧力容器４が原子炉遮蔽壁６まで上がったら、一旦、原子炉圧力容器４の引き上げを止め、原子炉圧力容器４の外周に外面上部遮蔽材２５を取付ける。
【００３３】
この際、原子炉圧力容器４下部のＣＲＤハウジング１０及びその近傍にまで外面上部遮蔽材２５を取付けるようにするには、原子炉圧力容器４下部の形状が複雑であるとか、遮蔽材が重量物であるにも拘らず下部用の遮蔽材は原子炉遮蔽壁６の上に支持させられない、などの問題があって、作業に時間が掛ってしまうため、圧力容器本体１３の下部は遮蔽用水２４で遮蔽させるようにしている。従って、遮蔽用水２４は、外面上部遮蔽材２５の下端よりも上のレベルまで入れるようにする。
【００３４】
原子炉圧力容器４に外面上部遮蔽材２５が取付けられたら、図３に示すように、図示しないクレーンで原子炉圧力容器４を引き上げ、圧力容器本体１３を外部へ搬出し、図４に示すように、輸送スキッド２８の上部に載せる。
【００３５】
すると、輸送スキッド２８の上部には外面下部遮蔽材２９が取付けられているので、原子炉圧力容器４下部の遮蔽用水２４で遮蔽されていた部分が外面下部遮蔽材２９で遮蔽されることとなる。
【００３６】
こうして、原子炉圧力容器４全体が遮蔽されたら、原子炉圧力容器４を横倒しにして処分施設へ搬送する。
【００３７】
このように、本実施の形態によれば、圧力容器本体１３の下部に遮蔽用水２４を注入して、外面上部遮蔽材２５で覆われていない部分を遮蔽用水２４で遮蔽させるようにしているので、簡単に圧力容器本体１３に外面上部遮蔽材２５を取付けて、確実に遮蔽を行わせることができる。
【００３８】
又、圧力容器本体１３下部にのみ、遮蔽用水２４を注入するようにしているので、遮蔽用水２４が少なくて済み、吊上げ重量を軽減させることが可能となる。
【００３９】
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。
【００４０】
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。
【００４１】
【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】本発明の実施の形態の一例の全体概略側方断面図である。
【図２】図１に続く作動図である。
【図３】図２に続く作動図である。
【図４】図３に続く作動図である。
【符号の説明】
４ 原子炉圧力容器
２４ 遮蔽用水
２５ 外面上部遮蔽材
２８ 輸送スキッド
２９ 外面下部遮蔽材[0001]
BACKGROUND OF THE INVENTION
The present invention relates to a method for carrying out a reactor pressure vessel. More specifically, the present invention relates to a method of carrying out a reactor pressure vessel that allows the reactor pressure vessel to be replaced within a short time without affecting the facility.
[0002]
[Prior art]
The nuclear power generation facility is designed with a predetermined useful life, and the facility is discarded when a predetermined useful life elapses.
[0003]
However, since the nuclear power generation facility actually has a sufficient margin for the determined service life, it is possible to extend the life of the nuclear power generation facility by replacing only the parts that have reached the end of their service life. It is.
[0004]
For this reason, it is necessary to establish a technique for exchanging parts that have reached the end of their lives. In this case, a representative example of the parts to be exchanged is a reactor pressure vessel.
[0005]
However, at present, there is no actual example of exchanging the reactor pressure vessel, and no exchanging technology has been established.
[0006]
[Problems to be solved by the invention]
When carrying out a reactor pressure vessel that has reached the end of its life from a nuclear power generation facility, it is important how to shield the activated reactor pressure vessel and how to carry it out to the outside without affecting the facility in a short time. .
[0007]
In view of the above circumstances, an object of the present invention is to provide a method for carrying out a reactor pressure vessel so that the reactor pressure vessel can be replaced in a short time without affecting the facility. .
[0008]
[Means for Solving the Problems]
In the present invention , the shielding water 24 is injected into the reactor pressure vessel 4 to be removed from the reactor containment vessel 1 so that the shielding water 24 is stored only in the lower part of the pressure vessel body 13. 1 is mounted on the upper part of the reactor shielding wall 6 surrounding the outer periphery of the pressure vessel main body 13 with an outer surface upper shielding material 25 covering the outer peripheral portion of the upper portion of the pressure vessel main body 13, and the reactor pressure vessel 4 is lifted up. A reactor pressure vessel carrying-out method characterized in that an outer surface upper shielding material 25 is attached to the outer periphery, and the reactor pressure vessel 4 and the outer surface upper shielding material 25 are integrally carried out of the reactor containment vessel 1. It is.
[0009]
In this case, when the pressure vessel main body 13 carried out of the reactor containment vessel 1 is placed on and supported by the transport skid 28, the outer pressure lower shielding material 29 attached to the upper portion of the transport skid 28 is used for the pressure vessel main body 13. The lower part may be covered.
[0010]
According to the present invention, the following effects can be obtained.
[0011]
When the reactor pressure vessel 4 is taken out from the reactor containment vessel 1, the shielding water 24 is injected into the pressure vessel body 13, and the shielding water 24 is stored in the lower portion of the pressure vessel body 13.
[0012]
When ready in this way, the reactor pressure vessel 4 is pulled up to some extent, and the outer surface upper shielding material 25 is attached to the outer periphery of the reactor pressure vessel 4.
[0013]
At this time, if the outer surface upper shielding member 25 is attached to the lower part of the reactor pressure vessel 4, the work takes time. Therefore, the lower part of the pressure vessel body 13 is shielded by the shielding water 24. Therefore, the shielding water 24 is introduced to a level above the lower end of the outer surface upper shielding material 25.
[0014]
When the outer surface upper shielding member 25 is attached to the reactor pressure vessel 4, the pulling up of the reactor pressure vessel 4 is resumed, the pressure vessel body 13 is carried out to the outside, and placed on the upper part of the transport skid 28.
[0015]
Then, since the outer surface lower shielding material 29 is attached to the upper part of the transport skid 28, the portion shielded by the shielding water 24 at the lower part of the reactor pressure vessel 4 is shielded by the outer surface lower shielding material 29. .
[0016]
When the entire reactor pressure vessel 4 is shielded in this way, the reactor pressure vessel 4 is laid down and transported to a disposal facility.
[0017]
In this way, the shielding water 24 is injected into the lower portion of the pressure vessel main body 13 so that the portion not covered with the outer surface upper shielding material 25 is shielded with the shielding water 24. The outer surface upper shielding member 25 can be attached to ensure the shielding.
[0018]
Further, since the shielding water 24 is injected only into the lower portion of the pressure vessel main body 13, the shielding water 24 is small and the lifting weight can be reduced.
[0019]
As described above, it is possible to replace the reactor pressure vessel 4 without affecting the facility in a short time.
[0020]
DETAILED DESCRIPTION OF THE INVENTION
Hereinafter, embodiments of the present invention will be described with reference to the drawings.
[0021]
1 to 4 show an example of an embodiment of the present invention.
[0022]
In the figure, 1 is a reactor containment vessel, 4 is a reactor pressure vessel accommodated in the reactor containment vessel 1, and 5 is a lower part of the reactor pressure vessel 4 provided at the bottom of the reactor containment vessel 1. A pedestal 6 for supporting the lower part of the pedestal 5 and a reactor shielding wall provided so as to surround the outer periphery of the reactor pressure vessel 4. The upper nozzle opening, 8 is a lower nozzle opening formed at a plurality of locations in the circumferential direction at the lower portion of the reactor shielding wall 6, and 9 is the reactor containment vessel 1 through the bellows (not shown) at the upper portion of the reactor pressure vessel 4. It is a bulkhead part for connecting to.
[0023]
The reactor pressure vessel 4 has a CRD housing 10 for taking control rods in and out at the lower part, and an upper nozzle 11 and a lower part on the side corresponding to the upper nozzle opening 7 and the lower nozzle opening 8, respectively. The pressure vessel main body 13 having the nozzle 12, the lid body 15 having a plurality of nozzles 14, and the stat bolt 16 that fastens the pressure vessel main body 13 and the lid body 15 are configured.
[0024]
A cylindrical body called a shroud 17 is attached to the lower part of the pressure vessel main body 13, and an upper lattice plate 18 attached to the upper part of the shroud 17 and a core support plate 19 attached to the intermediate part. A core region 20 is formed therebetween.
[0025]
In the figure, 21 and 22 are opening closing plates for closing the upper nozzle opening 7 and the lower nozzle opening 8, respectively, 23 is a fixing bolt for fixing the pressure vessel main body 13 and the upper part of the reactor shielding wall 6; In FIG. 2, 24 is shielding water injected into the pressure vessel main body 13, 25 is an outer surface upper shielding material attached so as to cover the outer peripheral portion of the upper portion of the pressure vessel main body 13, and 26 is inner surface shielding attached to the upper surface of the shroud 17. 27, a suspension member that is attached to the lid body 15 and lifts the pressure vessel main body 13 with a crane (not shown). In FIG. 4, 28 is a transport for placing and supporting the pressure vessel main body 13 carried outside. A skid 29 is an outer lower shielding material attached to the upper part of the transport skid 28 for covering the outer peripheral portion of the lower portion of the pressure vessel main body 13.
[0026]
Next, the operation will be described.
[0027]
When the reactor pressure vessel 4 is taken out 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 an external device are cut off, and the upper nozzle 11 The lower nozzle 12 cuts a portion that buffers the reactor shielding wall 6.
[0028]
And the opening part of the cut | disconnected upper nozzle 11, the lower nozzle 12, and the CRD housing 10 is closed, and the upper nozzle opening part 7 and the lower nozzle opening part 8 are each closed with the opening closing plates 21 and 22, as needed. To do.
[0029]
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 main body 13 is disassembled, and parts other than the components to be removed simultaneously with the reactor pressure vessel 4 And the inner shield 26 is attached to the upper surface of the shroud 17.
[0030]
When the inner shielding member 26 is thus attached to the upper surface of the shroud 17, the lid 15 is attached to the pressure vessel body 13 again, and the suspension member 27 is further attached to the lid 15, so that the nozzle 14 formed on the lid 15 The shielding water 24 is injected into the pressure vessel body 13 so that the shielding water 24 is stored in the lower portion of the pressure vessel body 13.
[0031]
When ready in this way, the fixing bolt 23 for fixing the pressure vessel main body 13 and the upper part of the reactor shielding wall 6 is removed, and the outer surface upper shielding member 25 in a state of being divided into a plurality of parts in the circumferential direction on the upper part of the reactor shielding wall 6. As shown in FIG. 2, the reactor pressure vessel 4 is pulled up via the suspension member 27 using a crane (not shown).
[0032]
When the reactor pressure vessel 4 rises to the reactor shielding wall 6, the reactor pressure vessel 4 is temporarily stopped from being pulled up, and the outer surface upper shielding member 25 is attached to the outer periphery of the reactor pressure vessel 4.
[0033]
At this time, in order to attach the outer surface upper shielding material 25 to the CRD housing 10 below the reactor pressure vessel 4 and the vicinity thereof, the shape of the lower portion of the reactor pressure vessel 4 is complicated, or the shielding material is heavy. However, since the lower shielding material cannot be supported on the reactor shielding wall 6, the operation takes time. 24 is shielded. Therefore, the shielding water 24 is introduced to a level above the lower end of the outer surface upper shielding material 25.
[0034]
When the outer surface upper shielding member 25 is attached to the reactor pressure vessel 4, as shown in FIG. 3, the reactor pressure vessel 4 is pulled up by a crane (not shown), and the pressure vessel body 13 is carried out to the outside, as shown in FIG. Then, it is placed on top of the transport skid 28.
[0035]
Then, since the outer surface lower shielding material 29 is attached to the upper part of the transport skid 28, the portion shielded by the shielding water 24 at the lower part of the reactor pressure vessel 4 is shielded by the outer surface lower shielding material 29. .
[0036]
When the entire reactor pressure vessel 4 is shielded in this way, the reactor pressure vessel 4 is laid down and transported to a disposal facility.
[0037]
As described above, according to the present embodiment, the shielding water 24 is injected into the lower portion of the pressure vessel body 13 so that the portion not covered with the outer surface upper shielding material 25 is shielded by the shielding water 24. The outer surface upper shielding member 25 can be easily attached to the pressure vessel main body 13 and can be shielded reliably.
[0038]
Further, since the shielding water 24 is injected only into the lower portion of the pressure vessel main body 13, the shielding water 24 is small and the lifting weight can be reduced.
[0039]
As described above, the reactor pressure vessel 4 can be exchanged in a short time without affecting the facility.
[0040]
It should be noted that the present invention is not limited to the above-described embodiment, and various modifications can be made without departing from the scope of the present invention.
[0041]
【The invention's effect】
As described above, according to the reactor pressure vessel carrying-out method of the present invention, it is possible to achieve an excellent effect that the reactor pressure vessel can be replaced without affecting the facility in a short time.
[Brief description of the drawings]
FIG. 1 is an overall schematic side sectional view of an example of an embodiment of the present invention.
FIG. 2 is an operation diagram subsequent to FIG. 1;
FIG. 3 is an operation diagram subsequent to FIG. 2;
FIG. 4 is an operation diagram following FIG. 3;
[Explanation of symbols]
4 Reactor pressure vessel 24 Shielding water 25 Outer surface upper shielding material 28 Transport skid 29 Outer surface lower shielding material

Claims (1)

原子炉格納容器（１）から搬出すべき原子炉圧力容器（４）の内部に遮蔽用水（２４）を注入して当該圧力容器本体（１３）の下部にのみ遮蔽用水（２４）が貯まった状態とし、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）の上部に圧力容器本体（１３）上部の外周部分を覆い得る外面上部遮蔽材（２５）を載せ、原子炉圧力容器（４）を引き上げてその外周に外面上部遮蔽材（２５）を取り付け、原子炉圧力容器（４）及び外面上部遮蔽材（２５）を一体的に原子炉格納容器（１）の外部へ搬出し、原子炉格納容器（１）の外部へ搬出した原子炉圧力容器（４）を輸送スキッド（２８）に載置して支持する時に、輸送スキッド（２８）の上部に取付けた外面下部遮蔽材（２９）で、圧力容器本体（１３）下部を覆うようにすることを特徴とする原子炉圧力容器搬出方法。A state in which the shielding water (24) is injected into the reactor pressure vessel (4) to be carried out of the reactor containment vessel (1) and the shielding water (24) is stored only in the lower portion of the pressure vessel body (13). The upper part of the outer surface which can cover the outer peripheral part of the upper part of the pressure vessel main body (13) on the upper part of the reactor shielding wall (6) surrounding the outer periphery of the pressure vessel main body (13) inside the reactor containment vessel (1) The shielding material (25) is placed, the reactor pressure vessel (4) is pulled up, the outer surface upper shielding material (25) is attached to the outer periphery thereof, and the reactor pressure vessel (4) and the outer surface upper shielding material (25) are integrated. When the reactor pressure vessel (4) carried out of the reactor containment vessel (1) and carried out of the reactor containment vessel (1) is placed on and supported by the transport skid (28), the transport skid ( 28) The outer surface lower shielding material (29) attached to the upper part of Reactor pressure vessel extraction methods, characterized by the body (13) so as to cover the bottom.
JP19479596A 1996-07-24 1996-07-24 Reactor pressure vessel removal method Expired - Lifetime JP3654716B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP19479596A JP3654716B2 (en) 1996-07-24 1996-07-24 Reactor pressure vessel removal method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP19479596A JP3654716B2 (en) 1996-07-24 1996-07-24 Reactor pressure vessel removal method

Publications (2)

Publication Number Publication Date
JPH1039076A JPH1039076A (en) 1998-02-13
JP3654716B2 true JP3654716B2 (en) 2005-06-02

Family

ID=16330391

Family Applications (1)

Application Number Title Priority Date Filing Date
JP19479596A Expired - Lifetime JP3654716B2 (en) 1996-07-24 1996-07-24 Reactor pressure vessel removal method

Country Status (1)

Country Link
JP (1) JP3654716B2 (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2000206294A (en) 1999-01-14 2000-07-28 Hitachi Ltd Method for bringing out large equipment
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
WO2001024199A1 (en) * 1999-09-29 2001-04-05 Hitachi, Ltd. Method of carrying equipment out of nuclear power plant
WO2001069609A1 (en) * 2000-03-15 2001-09-20 Hitachi, Ltd. Method of handling equipment

Also Published As

Publication number Publication date
JPH1039076A (en) 1998-02-13

Similar Documents

Publication Publication Date Title
JP6402094B2 (en) Refueling method for nuclear reactor
JPH08240693A (en) Method for removal and cutting of structure at inside of reactor pressure vessel
JP3654716B2 (en) Reactor pressure vessel removal method
US6643349B2 (en) Method of removing a large-sized apparatus from a reactor building of a nuclear plant
JP3586469B2 (en) Method of removing components located inside a reactor pressure vessel of a reactor installation
JP3595416B2 (en) Reactor pressure vessel unloading method
JP3435270B2 (en) How to bring in the reactor pressure vessel
JP3343447B2 (en) How to unload the reactor pressure vessel
JP2764871B2 (en) How to replace components inside the containment vessel of a nuclear reactor
KR20150023449A (en) Optimised method for loading radioactive elements into a package
JP4055157B2 (en) Reactor pressure vessel replacement method
JP3101095B2 (en) Decommissioning method and system for reactor pressure vessel
JP4253888B2 (en) Reactor pressure vessel unloading device
JPS643104Y2 (en)
JP2004144698A (en) Method for housing reactor internal structure
JPH07218696A (en) Replace method for reeactor pressure vessel
JP3851626B2 (en) Reactor pressure vessel loading method
JP4177964B2 (en) How to carry out reactor internals
RU2162U1 (en) RECEPTION DEVICE FOR SPENT NUCLEAR FUEL
JP2019078766A (en) Device storage
JP2004264206A (en) Method and device for carrying out pipe cutting tool and structure in reactor
JP2000284093A (en) Treatment method of reactor pressure vessel
EP0313887A2 (en) One-piece temporary gap seal between reactor vessel and closure head
JP4096911B2 (en) Reactor pressure vessel replacement method
JPH0552478B2 (en)

Legal Events

Date Code Title Description
A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20040518

A521 Written amendment

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20040716

TRDD Decision of grant or rejection written
A01 Written decision to grant a patent or to grant a registration (utility model)

Free format text: JAPANESE INTERMEDIATE CODE: A01

Effective date: 20050301

A61 First payment of annual fees (during grant procedure)

Free format text: JAPANESE INTERMEDIATE CODE: A61

Effective date: 20050301

R150 Certificate of patent or registration of utility model

Free format text: JAPANESE INTERMEDIATE CODE: R150

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20080311

Year of fee payment: 3

S531 Written request for registration of change of domicile

Free format text: JAPANESE INTERMEDIATE CODE: R313531

S533 Written request for registration of change of name

Free format text: JAPANESE INTERMEDIATE CODE: R313533

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20080311

Year of fee payment: 3

R350 Written notification of registration of transfer

Free format text: JAPANESE INTERMEDIATE CODE: R350

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20090311

Year of fee payment: 4

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20100311

Year of fee payment: 5

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20110311

Year of fee payment: 6

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20120311

Year of fee payment: 7

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20120311

Year of fee payment: 7

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20130311

Year of fee payment: 8