JPH07218696A - Replace method for reeactor pressure vessel - Google Patents
Replace method for reeactor pressure vesselInfo
- Publication number
- JPH07218696A JPH07218696A JP1439694A JP1439694A JPH07218696A JP H07218696 A JPH07218696 A JP H07218696A JP 1439694 A JP1439694 A JP 1439694A JP 1439694 A JP1439694 A JP 1439694A JP H07218696 A JPH07218696 A JP H07218696A
- Authority
- JP
- Japan
- Prior art keywords
- pressure vessel
- reactor
- vessel
- shielding wall
- 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.)
- Pending
Links
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【0001】[0001]
【産業上の利用分野】本発明は原子炉圧力容器を新替え
するために、原子炉圧力容器を撤去するに際し、特に圧
力容器の周辺の構造物に与える影響を少なくすることの
できる原子炉圧力容器の新替え方法に関するものであ
る。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor pressure which can reduce the influence on the structure around the pressure vessel when the reactor pressure vessel is removed in order to replace the reactor pressure vessel with a new one. It relates to a new container replacement method.
【0002】[0002]
【従来の技術】原子力発電所等においては原子炉建屋躯
体内に格納容器が収容され、その格納容器内には遮蔽壁
で囲まれた原子炉圧力容器が設置されている。2. Description of the Related Art In a nuclear power plant or the like, a containment vessel is housed in a reactor building body, and a reactor pressure vessel surrounded by a shielding wall is installed in the containment vessel.
【0003】[0003]
【発明が解決しようとする課題】ところで、原子炉も所
定耐用年数を経過すると廃炉となる。廃炉となった場
合、最も傷む原子炉圧力容器を撤去して新規な圧力容器
に新替えすることになるが、使用済みの圧力容器を撤去
する際、圧力容器の周辺の構造物をそのまま残せれば、
新替えに伴う撤去範囲も少なくなる。また、原子炉圧力
容器には各種配管が接続されると共にその配管も圧力容
器の周囲に狭い隙間を隔てて形成される遮蔽壁を貫通し
て配設されていることから、圧力容器の撤去から新替え
に至る工事の簡素化、工期の短縮化を考慮すると、圧力
容器の周囲の構造物に影響を与えないことが望まれる。By the way, the reactor is also decommissioned after a predetermined useful life. In the case of decommissioning, the most damaged reactor pressure vessel will be removed and replaced with a new pressure vessel, but when removing a used pressure vessel, leave the structure around the pressure vessel as it is. If
The range of removal due to new replacement is also reduced. Also, since various pipes are connected to the reactor pressure vessel and the pipes are also arranged through the shielding wall formed around the pressure vessel with a narrow gap, it is necessary to remove the pressure vessel. Considering the simplification of construction work and the shortening of the construction period, it is desirable that the structure around the pressure vessel is not affected.
【0004】本発明は上記事情を考慮して創案されたも
のである。本発明は圧力容器の撤去から新替えに至る工
事の簡素化、工期の短縮化を達成することのできる原子
炉圧力容器の新替え方法を提供することを目的とする。The present invention was made in consideration of the above circumstances. An object of the present invention is to provide a new reactor pressure vessel replacement method capable of simplifying the work from removal of the pressure vessel to new replacement and shortening the construction period.
【0005】[0005]
【課題を解決するための手段】第1の発明にあっては原
子炉建屋躯体内の格納容器内に原子炉遮蔽壁で囲まれて
収容された原子炉圧力容器を新替えするために圧力容器
を躯体外に撤去する方法において、上記遮蔽壁を貫通し
て圧力容器に接続される配管を遮蔽壁の内側の位置で切
断して切り離し、基礎上に据え付けられた圧力容器の固
定を解除した後、圧力容器を上方に開放された格納容器
および躯体外に吊り上げて撤去するようにしたものであ
る。According to the first aspect of the present invention, there is provided a pressure vessel for replacing a reactor pressure vessel housed in a containment vessel inside a reactor building body surrounded by a reactor shield wall. In the method of removing the outside of the body, after cutting the pipe that penetrates the shielding wall and is connected to the pressure vessel at a position inside the shielding wall to separate it, after releasing the fixation of the pressure vessel installed on the foundation The pressure vessel is lifted to the outside of the containment vessel and the skeleton that are open upward, and is removed.
【0006】また、第2の発明は原子炉建屋躯体内の格
納容器内に原子炉遮蔽壁で囲まれて収容された原子炉圧
力容器を新替えするために圧力容器を躯体外に撤去する
方法において、上記遮蔽壁を貫通して圧力容器に接続さ
れる配管を上記遮蔽壁の内側および外側の位置でそれぞ
れ切断して撤去すると共に格納容器から圧力容器に向け
て水平に延出されるバルクヘッドを格納容器側に一部を
残存させつつ遮蔽壁の外側の位置で切断して上方に開放
された圧力容器外に吊り上げ撤去し、基礎上に据え付ら
れた圧力容器および遮蔽壁の固定を解除した後、これら
圧力容器および遮蔽壁を上方に吊り上げて撤去するよう
にしたものである。A second aspect of the present invention is a method of removing the pressure vessel outside the body to replace the reactor pressure vessel which is housed in the containment vessel inside the reactor building body surrounded by the reactor shielding wall. In, the bulkhead that extends horizontally from the containment vessel toward the pressure vessel while cutting and removing the pipes penetrating the shielding wall and connected to the pressure vessel at positions inside and outside the shielding wall, respectively. While leaving a part on the side of the containment vessel, cut at a position outside the shielding wall, lifted up outside the pressure vessel opened upward, and removed, and fixed the pressure vessel and the shielding wall installed on the foundation. After that, the pressure vessel and the shielding wall are lifted up and removed.
【0007】[0007]
【作用】第1の発明においては遮蔽壁を貫通して圧力容
器に接続される配管が圧力容器を撤去するうえで障害と
なることから、配管を圧力容器とこれを覆う遮蔽壁との
間の位置で切断するようにしたものである。したがっ
て、遮蔽壁を残存させておいて圧力容器を撤去すること
を可能にしたものである。In the first aspect of the present invention, the pipe that penetrates the shield wall and is connected to the pressure container is an obstacle to removing the pressure container. Therefore, the pipe between the pressure container and the shield wall that covers the pipe is blocked. It is designed to be cut at the position. Therefore, it is possible to remove the pressure vessel while leaving the shielding wall.
【0008】第2の発明においては圧力容器の撤去に伴
ってこれを覆う遮蔽壁を撤去するには遮蔽壁を貫通して
圧力容器に接続される配管および遮蔽壁の上方に格納容
器から水平に延出されるバルクヘッドが障害となる。こ
のため、配管を遮蔽壁の内側および外側の位置でそれぞ
れ切断すると共に、バルクヘッドを格納容器に一部を残
存させて遮蔽壁の外側の位置で切断して圧力容器から切
り離すようにしたものである。圧力容器および遮蔽壁を
撤去しても格納容器にはバルクヘッドの一部が残るた
め、新替え時においてその切断部に切り離されて撤去さ
れたバルクヘッドを取り付ければ、バルクヘッドの再利
用が可能となる。In the second aspect of the present invention, in order to remove the shield wall covering the pressure vessel with the removal of the pressure vessel, the pipe passing through the shield wall and connected to the pressure vessel and above the shield wall are provided horizontally from the storage vessel. The extended bulkhead is an obstacle. For this reason, the pipes are cut inside and outside the shielding wall, respectively, and the bulkhead is partially left in the containment vessel and cut outside the shielding wall to separate it from the pressure vessel. is there. Even if the pressure vessel and the shielding wall are removed, a part of the bulkhead remains in the containment vessel, so the bulkhead can be reused by attaching the removed bulkhead to the cutting part at the time of replacement. Becomes
【0009】[0009]
【実施例】以下、本発明の一実施例を添付図面に基づい
て詳述する。An embodiment of the present invention will be described in detail below with reference to the accompanying drawings.
【0010】図1および図2に示すように、原子力発電
所などの原子炉建屋躯体1内に原子炉格納容器2が収容
され、この原子炉格納容器2内には原子炉遮蔽壁3で覆
われた原子炉圧力容器4が格納されている。この原子炉
圧力容器4の使用が所定年数を経過して寿命に達する
と、新替えするために、その使用済みの原子炉圧力容器
4を躯体1外に撤去することになる。As shown in FIGS. 1 and 2, a reactor containment vessel 2 is housed in a reactor building body 1 such as a nuclear power plant, and the reactor containment vessel 2 is covered with a reactor shield wall 3. The opened reactor pressure vessel 4 is stored. When the life of the reactor pressure vessel 4 reaches a life after a predetermined number of years has passed, the used reactor pressure vessel 4 is removed to the outside of the body 1 for a new replacement.
【0011】原子炉圧力容器4は金属製保温材5(5a
〜5e)で被覆されており、原子炉圧力容器4とこれを
覆うように原子炉格納容器2から水平に延出されるリン
グ状のバルクヘッド6との間にはベローズ7が介設され
ている。また、原子炉圧力容器4には各種配管8(8a
〜8e)が接続されていることから、撤去するためには
これら保温材5、ベローズ7および配管8を撤去処理す
ることになる。The reactor pressure vessel 4 includes a metal heat insulating material 5 (5a
5e), a bellows 7 is provided between the reactor pressure vessel 4 and a ring-shaped bulkhead 6 extending horizontally from the reactor containment vessel 2 so as to cover the reactor pressure vessel 4. . Further, the reactor pressure vessel 4 has various pipes 8 (8a
8e) are connected, the heat insulating material 5, the bellows 7 and the pipe 8 are removed in order to remove them.
【0012】先ず、図2に示すように原子炉圧力容器4
を覆う金属製保温材5を撤去すると共に、図1に示すよ
うに、原子炉格納容器2から原子力圧力容器4を覆うよ
うに延出されるバルクヘッド6と原子炉格納容器4との
間のベローズ7を切断して撤去する。次いで、原子炉圧
力容器4に接続される各種配管8を撤去する。これらの
配管8は原子炉圧力容器4を覆う遮蔽壁3を貫通するエ
ルボ11を介して原子炉圧力容器2に形成されたノズル
部12に接続されていることから、圧力容器4と遮蔽壁
3との間のノズル部12を溶断して原子炉圧力容器4か
ら切り離される。また、原子炉圧力容器4は基礎となる
ペデスタル13上にボルト(図示せず)で固定されてい
るので、このボルトを除去すれば、ペデスタル上13の
原子炉圧力容器4の固定を解除することができる。First, as shown in FIG. 2, the reactor pressure vessel 4
The bellows between the bulkhead 6 and the reactor containment vessel 4 extending from the reactor containment vessel 2 so as to cover the nuclear pressure vessel 4 are removed while removing the metal heat insulating material 5 covering the same. Cut 7 and remove. Next, various pipes 8 connected to the reactor pressure vessel 4 are removed. Since these pipes 8 are connected to the nozzle portion 12 formed in the reactor pressure vessel 2 through the elbow 11 penetrating the shield wall 3 covering the reactor pressure vessel 4, the pressure vessel 4 and the shield wall 3 are connected. The nozzle portion 12 between and is melted and separated from the reactor pressure vessel 4. Further, the reactor pressure vessel 4 is fixed to the pedestal 13 which is the base with bolts (not shown). Therefore, if this bolt is removed, the fixation of the reactor pressure vessel 4 on the pedestal 13 can be released. You can
【0013】一方、図3に示すように、原子炉圧力容器
4の上方の躯体1には天井クレーン14が設置されてお
り、この天井クレーン14で原子炉格納容器2の上蓋1
5を吊り上げて格納容器2を上方に開放する。吊り上げ
られた上蓋15は躯体1内に形成された平坦な載置部1
6に仮置される。また、躯体1の上部には開口部17を
開閉するスライド式仕切板18が設けられ、この仕切板
18を移動させれば、躯体1の上部が開放されるので、
原子炉圧力容器4を大型クレーン19で吊り上げて躯体
1外に撤去する。なお、原子炉圧力容器4を吊り上げる
際には躯体1の上部のビーム21上で原子炉圧力容器4
をシート状仮設エアロック22で覆って撤去することに
なる。On the other hand, as shown in FIG. 3, an overhead crane 14 is installed in the body 1 above the reactor pressure vessel 4, and the ceiling crane 14 allows the upper lid 1 of the reactor containment vessel 2 to be installed.
5 is lifted to open the storage container 2 upward. The suspended upper lid 15 is a flat mounting portion 1 formed in the body 1.
Temporarily placed at 6. Further, a slide type partition plate 18 that opens and closes the opening 17 is provided on the upper part of the frame 1, and if the partition plate 18 is moved, the upper part of the frame 1 is opened,
The reactor pressure vessel 4 is lifted by a large crane 19 and removed outside the skeleton 1. When the reactor pressure vessel 4 is lifted, the reactor pressure vessel 4 is mounted on the beam 21 above the frame 1.
The sheet-like temporary airlock 22 is covered and removed.
【0014】原子炉圧力容器4の撤去が完了した後、新
規な原子炉圧力容器は大型クレーン19で躯体1上に吊
り上げられて格納容器2内に搬入されることなる。After the removal of the reactor pressure vessel 4 is completed, the new reactor pressure vessel is hoisted on the skeleton 1 by the large crane 19 and carried into the containment vessel 2.
【0015】このように原子炉圧力容器4に接続される
配管8を圧力容器4と遮蔽壁3との間で切断すれば、圧
力容器4を撤去しても溶接構造の格納容器2に影響を与
えることなく、遮蔽壁3および各種配管8を存置したま
まで原子炉圧力容器4を撤去することが可能であり、新
替え後においてはこれら遮蔽壁3および配管8は再利用
することができる。特に、遮蔽壁3は鋼製型枠にコンク
リートを充填してなるものであることから、遮蔽壁3を
残存させておけば、原子炉圧力容器4の撤去が容易とな
ると共に撤去期間も短縮できる。If the pipe 8 connected to the reactor pressure vessel 4 is cut between the pressure vessel 4 and the shielding wall 3 in this way, even if the pressure vessel 4 is removed, the containment vessel 2 having a welded structure is affected. It is possible to remove the reactor pressure vessel 4 with the shielding wall 3 and the various pipes 8 left without being provided, and the shielding wall 3 and the pipe 8 can be reused after a new replacement. In particular, since the shielding wall 3 is made by filling the steel formwork with concrete, if the shielding wall 3 is left, the reactor pressure vessel 4 can be easily removed and the removal period can be shortened. .
【0016】次に第2の発明について説明する。Next, the second invention will be described.
【0017】第2の発明においては原子炉圧力容器4の
撤去に伴いこれを覆う遮蔽壁3も撤去するようにしたも
のである。他の構造物との取り合いや薄肉の遮蔽壁を採
用する場合には原子炉圧力容器4の撤去と共に遮蔽壁4
を撤去することが要請される場合がある。In the second aspect of the invention, the shield wall 3 covering the reactor pressure vessel 4 is also removed when the reactor pressure vessel 4 is removed. In the case of using another structure or a thin shielding wall, the shielding wall 4 should be removed together with the removal of the reactor pressure vessel 4.
May be required to be removed.
【0018】そこで、図1および図2において、上記第
1の発明と同様に金属製保温材5を撤去すると共に遮蔽
壁3を貫通して原子炉圧力容器4に接続される各種配管
8を遮蔽壁3の内側および外側の位置でそれぞれ切断し
てエルボ(図中斜線部)11を撤去する。また、原子炉
遮蔽壁3を覆うように原子炉格納容器2から水平に延出
されるバルクヘッド6が遮蔽壁3を上方に撤去するうえ
で障害となることから、図4に示すように、バルクヘッ
ド6と原子炉圧力容器4との間を切断撤去することにな
る。すなわち、バルクヘッド6にはベローズ7の上部が
取り付けられ、このベローズ7の下端部は原子炉圧力容
器4から水平に延出されるリング状の取合部23に取り
付けられているため、ベローズ6の上部(図中A)を切
断すると共に取合部23を原子炉圧力容器4のフランジ
部24の径内(図中B)で切断して撤去する。Therefore, in FIGS. 1 and 2, the metallic heat insulating material 5 is removed and various pipes 8 penetrating the shielding wall 3 and connected to the reactor pressure vessel 4 are shielded as in the first invention. The elbow (hatched portion in the figure) 11 is removed by cutting at the inner and outer positions of the wall 3. In addition, since the bulkhead 6 extending horizontally from the reactor containment vessel 2 so as to cover the reactor shield wall 3 becomes an obstacle in removing the shield wall 3 upward, as shown in FIG. The space between the head 6 and the reactor pressure vessel 4 will be cut and removed. That is, the upper portion of the bellows 7 is attached to the bulkhead 6, and the lower end portion of the bellows 7 is attached to the ring-shaped joining portion 23 that extends horizontally from the reactor pressure vessel 4. The upper part (A in the drawing) is cut, and the connecting portion 23 is cut and removed within the diameter (B in the drawing) of the flange portion 24 of the reactor pressure vessel 4.
【0019】次いで、図3および図4に示すように、原
子炉格納容器2を上部の開放すべく、天井クレーン14
で原子炉格納容器2の上蓋15を吊り上げて躯体1に形
成された載置部16に仮置し、バルクヘッド6に吊上げ
用ピース25を取り付け、バルクヘッド6を吊上げ用ピ
ース25を介して天井クレーン14で保持しつつ、バル
クヘッド6を原子炉遮蔽壁3の外径外で切断する。この
切断によりバルクヘッド6は格納容器2に基端部26を
残存させつつ切り離されて天井クレーン14から吊り下
げられた状態となる。吊り下げられたバルクヘッド6は
天井クレーン14で躯体1の載置部16に仮置される。Next, as shown in FIGS. 3 and 4, the overhead crane 14 is used to open the upper containment vessel 2.
Then, the upper lid 15 of the reactor containment vessel 2 is hung up and temporarily placed on the placing portion 16 formed on the skeleton 1, the lifting piece 25 is attached to the bulkhead 6, and the bulkhead 6 is hung through the lifting piece 25 to the ceiling. While being held by the crane 14, the bulkhead 6 is cut outside the outer diameter of the reactor shielding wall 3. By this cutting, the bulkhead 6 is separated from the storage container 2 while leaving the base end portion 26 thereof and is suspended from the overhead crane 14. The suspended bulkhead 6 is temporarily placed on the placing portion 16 of the skeleton 1 by the overhead crane 14.
【0020】原子炉遮蔽壁3はベデスタル13上にボル
ト(図示せず)で固定されているので、このボルトを取
り外して、原子炉遮蔽壁3の固定を解除する。Since the reactor shield wall 3 is fixed on the pedestal 13 with bolts (not shown), the bolts are removed and the reactor shield wall 3 is unfixed.
【0021】この後、上記第1の発明と同様に原子炉圧
力容器4は大型クレーン19で吊り上げてエアロック2
2で覆われて躯体1外に撤去することになるが、原子炉
遮蔽壁3は原子炉圧力容器4の撤去の後あるいは原子炉
圧力容器4と一体的に大型クレーン19で撤去されるこ
とになる。After that, the reactor pressure vessel 4 is lifted by the large crane 19 and the airlock 2 is moved as in the first invention.
It is covered with 2 and will be removed to the outside of the skeleton 1, but the reactor shield wall 3 will be removed by the large crane 19 after the removal of the reactor pressure vessel 4 or integrally with the reactor pressure vessel 4. Become.
【0022】原子炉圧力容器4および原子炉遮蔽壁3の
撤去後、新規な原子炉圧力容器およい遮蔽壁が大型クレ
ーン19で格納容器2内に搬入されることになる。この
場合、載置部16に仮置されていたバルクヘッド6は天
井クレーン14で吊り上げられて格納容器2内に残され
た基端部26に取り付けられて再利用される。After the reactor pressure vessel 4 and the reactor shield wall 3 are removed, a new reactor pressure vessel and a good shield wall are carried into the containment vessel 2 by the large crane 19. In this case, the bulkhead 6 temporarily placed on the placing portion 16 is lifted by the overhead crane 14 and attached to the base end portion 26 left in the storage container 2 for reuse.
【0023】このように第2の発明にあっては原子炉圧
力容器4の撤去に際し、原子炉遮蔽壁3を撤去しても、
遮蔽壁3を撤去するうえで障害となるバルクヘッド6を
格納容器2に一部を残存させつつ遮蔽壁3の外側の位置
で切断するので、溶接構造の格納容器2に与える影響が
なく、工事の簡素化、工期の短期化を達成できる。ま
た、新替え時においてはバルクヘッド6の再利用も可能
となる。As described above, according to the second aspect of the present invention, when the reactor pressure vessel 4 is removed, even if the reactor shield wall 3 is removed,
Since the bulkhead 6 which is an obstacle in removing the shield wall 3 is cut off at a position outside the shield wall 3 while leaving a part of the bulkhead 6 in the storage container 2, there is no effect on the storage container 2 having a welded structure, and the construction work can be performed. Can be simplified and the construction period can be shortened. In addition, the bulkhead 6 can be reused at the time of new replacement.
【0024】[0024]
【発明の効果】以上要するに本発明によれば、次の如き
優れた効果を発揮する。In summary, according to the present invention, the following excellent effects are exhibited.
【0025】(1) 請求項1においては原子炉圧力容器に
接続される配管を原子炉圧力容器とこれを覆う原子炉遮
蔽壁との間で切断するので、原子炉圧力容器を撤去して
も格納容器に与える影響が少なく、しかも遮蔽壁を残存
させておくことができるので、撤去作業の簡素化を図る
ことができる。(1) In claim 1, since the pipe connected to the reactor pressure vessel is cut between the reactor pressure vessel and the reactor shielding wall covering the same, even if the reactor pressure vessel is removed. Since the influence on the storage container is small and the shielding wall can be left, the removal work can be simplified.
【0026】(2) 請求項2においては格納容器から原子
炉圧力容器に延出されるバルクヘッドを格納容器側に一
部を残存させつつ遮蔽壁の外側の位置で切断撤去するの
で、圧力容器および遮蔽壁を撤去しても格納容器に与え
る影響がなく、工事の簡素化、工期の短期化を達成でき
ると共にバルクヘッドの再利用も可能である。(2) In the second aspect, the bulkhead extending from the containment vessel to the reactor pressure vessel is cut and removed at a position outside the shielding wall while leaving a part of the bulkhead on the side of the containment vessel. Even if the shielding wall is removed, it does not affect the containment vessel, which simplifies the construction work and shortens the construction period, and also enables reuse of the bulkhead.
【図1】原子炉圧力容器の格納状態を示す断面図であ
る。FIG. 1 is a cross-sectional view showing a stored state of a reactor pressure vessel.
【図2】原子炉圧力容器の周辺構造を示す断面図であ
る。FIG. 2 is a cross-sectional view showing a peripheral structure of a reactor pressure vessel.
【図3】原子炉圧力容器の撤去状態を示す断面図であ
る。FIG. 3 is a cross-sectional view showing a removed state of the reactor pressure vessel.
【図4】第2の発明を示すための説明図である。FIG. 4 is an explanatory diagram showing a second invention.
1 躯体 2 格納容器 3 原子炉遮蔽壁 4 原子炉圧力容器 6 バルクヘッド 8 配管 13 基礎となるペデスタル 1 Building 2 Containment Vessel 3 Reactor Shielding Wall 4 Reactor Pressure Vessel 6 Bulkhead 8 Piping 13 Base Pedestal
Claims (2)
遮蔽壁で囲まれて収容された原子炉圧力容器を新替えす
るために圧力容器を躯体外に撤去する方法において、上
記遮蔽壁を貫通して圧力容器に接続される配管を遮蔽壁
の内側の位置で切断して切り離し、基礎上に据え付けら
れた圧力容器の固定を解除した後、圧力容器を上方に開
放された格納容器および躯体外に吊り上げて撤去するよ
うにしたことを特徴とする原子炉圧力容器の新替え方
法。1. A method for removing a pressure vessel outside the body to replace a reactor pressure vessel housed in a containment vessel inside a reactor building body surrounded by a reactor shielding wall, After cutting through the pipe connected to the pressure vessel at a position inside the shielding wall to disconnect it, and after releasing the fixation of the pressure vessel installed on the foundation, the pressure vessel is opened to the upper side of the containment vessel and A new method for replacing a reactor pressure vessel, which is characterized in that it is lifted outside the body and removed.
遮蔽壁で囲まれて収容された原子炉圧力容器を新替えす
るために圧力容器を躯体外に撤去する方法において、上
記遮蔽壁を貫通して圧力容器に接続される配管を上記遮
蔽壁の内側および外側の位置でそれぞれ切断して撤去す
ると共に、格納容器から圧力容器に向けて水平に延出さ
れるバルクヘッドを格納容器側に一部を残存させつつ遮
蔽壁の外側の位置で切断して上方に吊り上げ撤去し、基
礎上に据え付られた圧力容器および遮蔽壁の固定を解除
した後、これら圧力容器および遮蔽壁を上方に開放され
た躯体外に吊り上げて撤去するようにしたことを特徴と
する原子炉圧力容器の新替え方法。2. A method of removing a pressure vessel outside the body to replace a reactor pressure vessel housed in a containment vessel inside a reactor building body surrounded by a reactor shield wall, While removing the pipes that penetrate through and are connected to the pressure vessel at positions inside and outside the shielding wall, respectively, and at the same time, remove the bulkhead horizontally extending from the containment vessel toward the pressure vessel to the containment vessel side. While leaving a part of it, cut it at a position outside the shielding wall, lift it up and remove it, and after releasing the fixation of the pressure vessel and the shielding wall installed on the foundation, move the pressure vessel and the shielding wall upward. A new method for replacing a reactor pressure vessel, which is characterized in that it is lifted to the outside of an open body and removed.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1439694A JPH07218696A (en) | 1994-02-08 | 1994-02-08 | Replace method for reeactor pressure vessel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1439694A JPH07218696A (en) | 1994-02-08 | 1994-02-08 | Replace method for reeactor pressure vessel |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH07218696A true JPH07218696A (en) | 1995-08-18 |
Family
ID=11859895
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP1439694A Pending JPH07218696A (en) | 1994-02-08 | 1994-02-08 | Replace method for reeactor pressure vessel |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH07218696A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2001069609A1 (en) * | 2000-03-15 | 2001-09-20 | Hitachi, Ltd. | Method of handling equipment |
US11581101B2 (en) | 2018-04-19 | 2023-02-14 | Korea Hydro & Nuclear Power Co., Ltd. | Method for decommissioning nuclear facilities |
-
1994
- 1994-02-08 JP JP1439694A patent/JPH07218696A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2001069609A1 (en) * | 2000-03-15 | 2001-09-20 | Hitachi, Ltd. | Method of handling equipment |
US11581101B2 (en) | 2018-04-19 | 2023-02-14 | Korea Hydro & Nuclear Power Co., Ltd. | Method for decommissioning nuclear facilities |
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