JPH02285287A - Nuclear reactor containment - Google Patents

Nuclear reactor containment

Info

Publication number
JPH02285287A
JPH02285287A JP1105914A JP10591489A JPH02285287A JP H02285287 A JPH02285287 A JP H02285287A JP 1105914 A JP1105914 A JP 1105914A JP 10591489 A JP10591489 A JP 10591489A JP H02285287 A JPH02285287 A JP H02285287A
Authority
JP
Japan
Prior art keywords
dry well
wall
reactor
nuclear reactor
containment vessel
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
JP1105914A
Other languages
Japanese (ja)
Inventor
Shuichi Kuriyama
栗山 修一
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
Original Assignee
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 Corp filed Critical Toshiba Corp
Priority to JP1105914A priority Critical patent/JPH02285287A/en
Publication of JPH02285287A publication Critical patent/JPH02285287A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To enable conducting a refueling work and work at the upper part of a dry well in parallel by providing a movable shielding body with which a space between a nuclear reactor pressure vessel and the dry well can be opened at the top part of a nuclear reactor shielding wall. CONSTITUTION:A top of a nuclear reactor shielding wall 2 is divided into two parts that are an inner surface side and an outer surface side, the inner surface side is constituted by a sleeve shaped shielding wall 6 as a movable shielding body and the wall 6 is held so as to be able to slide vertically along a fixed shielding wall 2A of the inner surface side. A space between a nuclear reactor pressure vessel 3 and a dry well 8 can be shielded by lifting up the wall 6 to block a space reaching to a nuclear reactor containment vessel 1. Considering about that a gap is generated between the vessel 1 and the wall 6 when the wall 6 is lifted up, a hanging wall for shielding is provided to the vessel 1 in order to shield a radiation passing through the gap. In this way, an amount of radiation to the dry well 8 is diminished and therefore there is no need to keep out an upper part of the dry well during a refuelling work.

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は原子炉圧力容器を収納した原子炉格納容器に係
り、特に、原子炉圧力容器からの放射線を遮蔽する原子
炉遮蔽壁を備えた原子炉格納容器に関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a nuclear reactor containment vessel that houses a nuclear reactor pressure vessel, and particularly relates to a nuclear reactor containment vessel that houses a nuclear reactor pressure vessel, and particularly to a nuclear reactor containment vessel that shields radiation from a nuclear reactor pressure vessel. This invention relates to a nuclear reactor containment vessel equipped with a shielding wall.

(従来の技術) 沸騰水型原子炉等の原子炉には原子炉格納容器が原子炉
建屋内に設置されており、この原子炉格納容器には、例
えば第5図および第6図(A)。
(Prior Art) In a nuclear reactor such as a boiling water reactor, a reactor containment vessel is installed in a reactor building. .

(B)に示すように原子炉圧力容器(以下RPVと略称
する)3が収容されている。このRPV3の周囲には、
第6図(A)、(8)に示すように原子炉遮蔽壁(以下
R8Wと略称する)2が設置され、RPV3を覆ってい
る。また、原子炉格納容器1内のドライウェル8には、
プラットホーム5が各機器のメンテナンス等のために設
けられている。
As shown in (B), a reactor pressure vessel (hereinafter abbreviated as RPV) 3 is accommodated. Around this RPV3,
As shown in FIGS. 6(A) and (8), a reactor shielding wall (hereinafter abbreviated as R8W) 2 is installed and covers the RPV 3. In addition, in the dry well 8 in the reactor containment vessel 1,
A platform 5 is provided for maintenance of each device.

ところで、第5図に示す原子炉格納容器1において、通
常運転時にはRPV3からの熱がR8W2とRPV3と
の間を上昇し、格納容器トップヘッド部12に熱または
圧力がn溜してしまうことが考えられる。このため、R
8W2と原子炉格納容器1間を開放し、上記の熱゛また
は圧力をドライウェル8に逃がすようにしている。
By the way, in the reactor containment vessel 1 shown in FIG. 5, during normal operation, heat from the RPV3 rises between R8W2 and RPV3, and heat or pressure may accumulate in the containment vessel top head section 12. Conceivable. For this reason, R
The space between 8W2 and the reactor containment vessel 1 is opened to allow the above heat or pressure to escape to the dry well 8.

また、燃料交換時において炉心から使用済燃料を引抜く
際にR8W2と原子炉格納容器1との間からドライウェ
ル8へ放射線7が照射されるおそれがある。この燃料交
換時には作業員が被曝する危険があるので、ドライウェ
ル8の上部は立入禁止としている。
Furthermore, there is a risk that the dry well 8 will be irradiated with radiation 7 from between the R8W2 and the reactor containment vessel 1 when the spent fuel is extracted from the core during fuel exchange. Since there is a risk that workers may be exposed to radiation during this fuel exchange, the upper part of the dry well 8 is prohibited from entry.

(発明が解決しようとする課題) 従来の原子炉格納容器おける原子炉遮蔽壁構造では、R
8W2と原子炉格納容器1との間が開放されているため
、燃料交換時にはドライウェル8の上部を立入禁止にし
なければならず、ここでの定期点検作業は燃料交換の間
、行なうことができないため、定期点検工程への影響が
大きくなっている。特に、鉄筋コンクリート製格納容器
(RCCV)では、機器搬出入用ハツチ4がドライウェ
ル8の上部に設置されており、このハツチ4が定期点検
時メインアクセス10であることから、ドライウェル8
の上部が燃料交換の間、作業員が立入禁止となることに
よる定期点検工程への影響は著しく大きいものとなって
いる。
(Problem to be solved by the invention) In the reactor shielding wall structure in the conventional reactor containment vessel, R
Since the space between 8W2 and reactor containment vessel 1 is open, the upper part of dry well 8 must be prohibited from entering during fuel exchange, and periodic inspection work here cannot be performed during fuel exchange. Therefore, the impact on the periodic inspection process is increasing. In particular, in a reinforced concrete containment vessel (RCCV), a hatch 4 for loading and unloading equipment is installed at the top of the dry well 8, and since this hatch 4 is the main access 10 during regular inspections, the dry well 8
The fact that workers are prohibited from entering the upper part of the fuel tank during fuel exchange has a significant impact on the periodic inspection process.

本発明は上述した事情を考慮してなされたちので、燃料
交換時のドライウェル上部への放射線を遮蔽することに
より、燃料交換とドライウェル上部での作業員による作
業とが並行して行ない得るようにし、また通常運転時に
は格納容器トップヘッド部への熱または圧力の滞溜を防
止する原子炉格納容器を提供することを目的とする。
The present invention has been made in consideration of the above-mentioned circumstances, so that by shielding radiation to the upper part of the dry well during fuel exchange, it is possible to perform fuel exchange and work by workers at the upper part of the dry well in parallel. Another object of the present invention is to provide a reactor containment vessel that prevents heat or pressure from accumulating in the top head portion of the containment vessel during normal operation.

〔発明の構成〕[Structure of the invention]

(課題を解決するための手段) 本発明による原子炉格納容器は、原子炉圧力容器を取り
囲み、この原子炉圧力容器からの放射線を遮蔽する原子
炉遮蔽壁を設置した原子炉格納容器において、上記原子
炉遮蔽壁の頂部に、上記原子炉圧力容器とドライウェル
との間を開放可能な可動式の遮蔽体を設けたことを特徴
とする。
(Means for Solving the Problems) A reactor containment vessel according to the present invention is a reactor containment vessel in which a reactor shielding wall surrounding a reactor pressure vessel and shielding radiation from the reactor pressure vessel is installed. The present invention is characterized in that a movable shield capable of opening the space between the reactor pressure vessel and the dry well is provided on the top of the reactor shielding wall.

(作用) 上記の構成を有する本発明においては、原子炉遮蔽壁の
頂部に設けた可動式の遮蔽体を燃料交換時に作動させ、
燃料交換時゛のドライウェル上部への放射線を遮蔽する
ことによって、燃料交換とドライウェル上部での作業と
が並行して行なうことができる。
(Function) In the present invention having the above configuration, the movable shield provided at the top of the reactor shielding wall is activated at the time of fuel exchange,
By shielding radiation to the upper part of the dry well during fuel exchange, fuel exchange and work on the upper part of the dry well can be performed in parallel.

また、通常運転時には、原子炉圧力容器とドライウェル
間を開放させることによって、格納容器トップヘッド部
に滞溜する熱または圧力をドライウェル内へ逃がすこと
ができる。
Furthermore, during normal operation, by opening the space between the reactor pressure vessel and the dry well, heat or pressure accumulated in the top head of the containment vessel can be released into the dry well.

(実施例) 以下、本発明の実施例を図面に基づいて説明する。なお
、従来の構成と同一または対応する部分には同一の符号
を用いて説明する。
(Example) Hereinafter, an example of the present invention will be described based on the drawings. Note that parts that are the same as or correspond to the conventional configuration will be described using the same reference numerals.

第1図は本発明に係る原子炉格納容器の第1実施例を示
す。この原子炉格納容器1内には原子炉圧力容器(RP
V)3が収容され、この原子炉格納容器3は図示しない
RPV支持ペデスタル上に据付けられる。このRPV支
持ペデスタル上部に筒状の原子炉遮蔽壁(R3W)2が
RPV3を覆うように設置される。
FIG. 1 shows a first embodiment of a nuclear reactor containment vessel according to the present invention. Inside this reactor containment vessel 1 is a reactor pressure vessel (RP).
This reactor containment vessel 3 is installed on an RPV support pedestal (not shown). A cylindrical reactor shielding wall (R3W) 2 is installed above the RPV support pedestal so as to cover the RPV 3.

また、原子炉格納容器1のドライウェル8にはブラット
ホーム5が設けられ、作業員はこのプラットホーム5上
で各機器のメンテナンス作業等を行なう。そして、ドラ
イウェル8の上部にはvi器搬出入用ハツチ4が設置さ
れ、このハツチ4が定期点検時のメインアクセスとなっ
ている。
Further, a platform 5 is provided in the dry well 8 of the reactor containment vessel 1, and workers perform maintenance work on each device on this platform 5. A hatch 4 for carrying in and out of the VI equipment is installed at the top of the dry well 8, and this hatch 4 serves as the main access during periodic inspections.

さらに、R8W2はその頂部が内周側と外周側とに2分
割され、このうち外周側は可動式の遮蔽体としてのスリ
ーブ状遮蔽壁6に構成され、この遮蔽壁6は内周側の固
定側遮蔽壁2Aに沿って上下方向に摺動可能に保持され
る。この可動式遮蔽壁6を吊上げ、原子炉格納容器1と
の間を閉塞することにより、RPV3とドライウェル8
との間を遮蔽することができるようになっている。可動
式遮蔽壁6を吊上げた際に原子炉格納容器1との間に隙
間が生じることを考慮し、その隙間から通過する放射線
を遮蔽するために原子炉格納容器1に遮蔽用たれ壁11
を設けである。
Furthermore, the top of R8W2 is divided into two parts, an inner circumferential side and an outer circumferential side, of which the outer circumferential side is constituted by a sleeve-shaped shielding wall 6 as a movable shield, and this shielding wall 6 is fixed on the inner circumferential side. It is held slidably in the vertical direction along the side shielding wall 2A. By lifting this movable shielding wall 6 and closing off the space between the reactor containment vessel 1 and the RPV 3 and the dry well 8.
It is now possible to shield between the Considering that a gap will be created between the movable shielding wall 6 and the reactor containment vessel 1 when it is lifted, a shielding wall 11 is installed in the reactor containment vessel 1 in order to shield radiation passing through the gap.
This is provided.

次に、本実施例の作用を説明する。Next, the operation of this embodiment will be explained.

通常運転時において、可動式遮蔽W16は第1図に実線
で示すように下げられ、RPV3とドライウェル8との
間が開放される。これにより、通常運転時の格納容器ト
ップヘッド部12に滞溜する熱または圧力をドライウェ
ル8内へ逃がすことができる。
During normal operation, the movable shield W16 is lowered as shown by the solid line in FIG. 1, and the space between the RPV 3 and the dry well 8 is opened. Thereby, the heat or pressure accumulated in the containment vessel top head section 12 during normal operation can be released into the dry well 8.

一方、燃料交換時においては、第1図に二点鎖線で示す
ように、可動式遮蔽壁6を吊り上げ、R8W2の頂部と
原子炉格納容器1との間を閉塞する。これにより、燃料
交換時に使用済の燃料棒を引き抜く際、可動式遮蔽壁6
によってドライウェル8へ照射される放射線を遮蔽する
ことができ、ドライウェル8の上部を立入禁止とするこ
とがなくなる。したがって、燃料交換作業とドライウェ
ル8上部での定期点検作業とを並行して行なうことがで
きる。
On the other hand, during fuel exchange, the movable shielding wall 6 is lifted up to close off the space between the top of R8W2 and the reactor containment vessel 1, as shown by the two-dot chain line in FIG. This allows the movable shielding wall 6 to be used when pulling out spent fuel rods during fuel exchange.
Therefore, the radiation irradiated to the dry well 8 can be shielded, and the upper part of the dry well 8 will not be prohibited from entering. Therefore, the fuel exchange work and the periodic inspection work on the upper part of the dry well 8 can be performed in parallel.

第2図は本発明に係る原子炉格納容器の第2実施例を示
し、前記第1実施例と同一部材には同一符号を付して説
明する。前記第1実施例ではR8W2の頂部を内周側と
外周側とに2分割してその外周1111部分を可動式遮
蔽壁6aとしたが、本実施例では第2図に示すように現
状のR8W2の頂部外周側に可動式スリーブ状遮蔽壁1
6を設けである。本実施例によれば、既存のR8W2の
外周側に可動式遮蔽壁16を設けであるので、製造効率
が良好となり、コストの低減が図れる。その他の構成お
よび作用は前記第1実施例と同一であるのでその説明を
省略する。
FIG. 2 shows a second embodiment of the reactor containment vessel according to the present invention, and the same members as those in the first embodiment will be described with the same reference numerals. In the first embodiment, the top of the R8W2 is divided into two parts, the inner circumference side and the outer circumference side, and the outer circumference 1111 part is used as the movable shielding wall 6a, but in this embodiment, as shown in FIG. A movable sleeve-shaped shielding wall 1 is installed on the outer circumferential side of the top of the
6 is provided. According to this embodiment, since the movable shielding wall 16 is provided on the outer peripheral side of the existing R8W2, manufacturing efficiency is improved and costs can be reduced. The other configurations and operations are the same as those of the first embodiment, so their explanation will be omitted.

第3図および第4図は本発明に係る原子炉格納容器の第
3実施例を示す。前記第1実施例と同一部材には同一符
号を付して説明を省略する。
3 and 4 show a third embodiment of the reactor containment vessel according to the present invention. The same members as those in the first embodiment are designated by the same reference numerals and their explanations will be omitted.

この実施例ではR8W2の頂部が原子炉格納容器1のド
ライウェル8の天井壁近傍まで延びており、R8W2の
頂部を内周側と外周側とに2分割してその外周側部分を
可動式遮蔽壁26としてR8W2の頂部内周側(固定側
)に対して周方向にスライド可能に構成している。そし
て、R8W2の頂部内周側と可動式遮蔽壁26には各々
周方向に所定間隔をおいて開口部2aおよび26aが開
閉可能に形成されている。
In this embodiment, the top of R8W2 extends to the vicinity of the ceiling wall of the dry well 8 of the reactor containment vessel 1, and the top of R8W2 is divided into two, an inner circumferential side and an outer circumferential side, and the outer circumferential side is a movable shield. The wall 26 is configured to be slidable in the circumferential direction relative to the inner peripheral side (fixed side) of the top of R8W2. Openings 2a and 26a are formed at predetermined intervals in the circumferential direction on the inner peripheral side of the top of R8W2 and on the movable shielding wall 26, respectively, so as to be openable and closable.

上記の構成において、通常運転時は第4図(A)に示す
ように、R8W2の頂部内周側の開口部2aと可動式遮
蔽壁26の開口部26aとの周方向の位置を一致させる
ことで、RPV3とドライウェル8との間が開放され、
連通している。これにより、格納容器トップヘッド部1
2に滞溜する熱または圧力を開口部2aおよび26aを
通してドライウェル8内へ逃がすことができる。
In the above configuration, during normal operation, as shown in FIG. 4(A), the opening 2a on the inner peripheral side of the top of R8W2 and the opening 26a of the movable shielding wall 26 should be aligned in the circumferential direction. Then, the space between RPV3 and dry well 8 is opened,
It's communicating. As a result, the containment vessel top head section 1
The heat or pressure accumulated in dry well 2 can be released into dry well 8 through openings 2a and 26a.

また、燃料交換時にはドライウェル8へ照射される放射
線(図示矢印で示す)7を遮蔽するために第4図(B)
に示すように可動式遮蔽!26を周方向にスライドさせ
てR8W2の頂部内周側の開口部2aと可動式遮蔽壁2
6の開口部26aとの周方向の位置を異ならせることに
より、RPV3とドライウェル8との間が遮蔽される。
Also, in order to shield the radiation (indicated by the arrow in the figure) 7 that is irradiated to the dry well 8 during fuel exchange, as shown in Fig. 4 (B).
Movable shielding as shown! 26 in the circumferential direction to connect the opening 2a on the inner peripheral side of the top of R8W2 and the movable shielding wall 2.
By differentiating the circumferential position from the opening 26a of the RPV 3 and the dry well 8, the space between the RPV 3 and the dry well 8 is shielded.

このように、第3実施例によれば、燃料交換時に可動式
遮蔽壁26を周方向にスライドさせるだけで、放射11
7が遮蔽されるので、前記第1実施例の可動式遮蔽壁6
のように吊上げることがなくなり、操作性が高まるとと
もに動力源が小さくて済む。その他の構成および作用は
前記第1実施例と同一であるのでその説明を省略する。
In this way, according to the third embodiment, the radiation 11
7 is shielded, the movable shielding wall 6 of the first embodiment
This eliminates the need for lifting, which improves operability and requires a smaller power source. The other configurations and operations are the same as those of the first embodiment, so their explanation will be omitted.

(発明の効果〕 以上の通り本発明によれば、原子炉遮蔽壁の頂部に可動
式の遮蔽体を設け、燃料交換時にこのi!!蔽体にて原
子炉圧力容器とドライウェル間を遮蔽することにより、
ドライウェルへの放射線層が減少するため、燃料交換時
にドライウェル上部を立入禁止にする必要はなくなる。
(Effects of the Invention) As described above, according to the present invention, a movable shield is provided at the top of the reactor shield wall, and the i!! shield shields the space between the reactor pressure vessel and the dry well during fuel exchange. By doing so,
Because the radiation layer into the drywell is reduced, there is no need to cordon off the top of the drywell during refueling.

その結果、燃料交換作業とドライウェル上部での定期点
検作業を並行して行なうことができ、定期点検工程の短
縮が可能となる。
As a result, fuel exchange work and periodic inspection work on the upper part of the dry well can be performed in parallel, making it possible to shorten the periodic inspection process.

また、通常運転時は原子炉圧力容器とドライウェル間を
開放することにより、格納容器トップヘッド部の熱また
は圧力溜りが防止されるため、信頼性の高い原子炉格納
容器を提供することができるという効果を奏する。
In addition, by opening the space between the reactor pressure vessel and the dry well during normal operation, heat or pressure buildup in the top head of the containment vessel is prevented, making it possible to provide a highly reliable reactor containment vessel. This effect is achieved.

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

第1図は本発明に係る原子炉格納容器の第1実施例を部
分的に示す構成図、第2図は本発明の第2実施例を部分
的に示す構成図、第3図は本発明の第3実施例を部分的
に示す構成図、第4図(A)および(B)は第3図の可
動式遮蔽壁の開放状態および遮蔽状態をそれぞれを示す
平断面図、第5図は従来の原子炉格納容器を示す構成図
、第6図(A)、(B)は第5図の原子炉遮蔽壁の構造
を示す縦断面図、部分平面図である。 1・・・原子炉格納容器、2・・・原子炉遮蔽壁(R8
W) 、3・・・原子炉圧力容器(RPV) 、6・・
・可動式遮蔽壁(遮蔽体)、8・・・ドライウェル、1
2・・・格納容器トップヘッド部。
FIG. 1 is a block diagram partially showing a first embodiment of a reactor containment vessel according to the present invention, FIG. 2 is a block diagram partially showing a second embodiment of the present invention, and FIG. 3 is a block diagram partially showing a first embodiment of a reactor containment vessel according to the present invention. FIGS. 4A and 4B are plan cross-sectional views showing the movable shielding wall in FIG. 3 in an open state and a shielded state, respectively. FIG. FIGS. 6(A) and 6(B) are a configuration diagram showing a conventional reactor containment vessel, and are a longitudinal sectional view and a partial plan view showing the structure of the reactor shielding wall in FIG. 5. 1... Reactor containment vessel, 2... Reactor shielding wall (R8
W), 3... Reactor pressure vessel (RPV), 6...
・Movable shielding wall (shielding body), 8...Dry well, 1
2... Containment vessel top head section.

Claims (1)

【特許請求の範囲】[Claims] 原子炉圧力容器を取り囲み、この原子炉圧力容器からの
放射線を遮蔽する原子炉遮蔽壁を設置した原子炉格納容
器において、上記原子炉遮蔽壁の頂部に、上記原子炉圧
力容器とドライウェルとの間を開放可能な可動式の遮蔽
体を設けたことを特徴とする原子炉格納容器。
In a reactor containment vessel equipped with a reactor shielding wall that surrounds a reactor pressure vessel and shields radiation from the reactor pressure vessel, a reactor shielding wall is provided at the top of the reactor shielding wall to connect the reactor pressure vessel and a dry well. A nuclear reactor containment vessel characterized by being provided with a movable shield that can be opened between.
JP1105914A 1989-04-27 1989-04-27 Nuclear reactor containment Pending JPH02285287A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1105914A JPH02285287A (en) 1989-04-27 1989-04-27 Nuclear reactor containment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1105914A JPH02285287A (en) 1989-04-27 1989-04-27 Nuclear reactor containment

Publications (1)

Publication Number Publication Date
JPH02285287A true JPH02285287A (en) 1990-11-22

Family

ID=14420133

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1105914A Pending JPH02285287A (en) 1989-04-27 1989-04-27 Nuclear reactor containment

Country Status (1)

Country Link
JP (1) JPH02285287A (en)

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