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JPH03194499A - Nuclear reactor containment air conditioning facility - Google Patents

Nuclear reactor containment air conditioning facility

Info

Publication number
JPH03194499A
JPH03194499A JP1331010A JP33101089A JPH03194499A JP H03194499 A JPH03194499 A JP H03194499A JP 1331010 A JP1331010 A JP 1331010A JP 33101089 A JP33101089 A JP 33101089A JP H03194499 A JPH03194499 A JP H03194499A
Authority
JP
Japan
Prior art keywords
cooling gas
grating
reactor containment
cooler
air conditioning
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
JP1331010A
Other languages
Japanese (ja)
Inventor
Koichi Yoshino
浩一 吉野
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 JP1331010A priority Critical patent/JPH03194499A/en
Publication of JPH03194499A publication Critical patent/JPH03194499A/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 cool the entire inside sufficiently by providing a cooler which cools the gas in nuclear reactor containment, an air blower which sends gas cooled by the cooler, and a cooling gas blowing duct. CONSTITUTION:The nuclear reactor containment air conditioning facilities 20 are equipped with the cooler which produces the cooling gas and the air blower which is connected to the cooler and sends the cooling gas. The cooling gas blowing duct 21 which is connected to the air blower and extends to a lower dry well 8B is terminated having a 1st blow-out opening 22 nearby an opening, i.e. below grating 13 as one end as usual. Then the cooling gas passing through the cooling gas blowing duct 11 when entering a nuclear reactor shield wall 5 is branched partially to flow in a branch pipe 23 and the remainder is jetted to below a grating 13 from a 1st blow-out opening 24. The jetted cooling gas becomes a swivel flow along the wall surface of the unclear reactor shield wall 5 to display cooling operation entirely in the shield wall 5.

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、原子炉格納容器内に設けられる原子炉格納容
器空調設備に係り、原子炉圧力容器付属機器点検用のグ
レーティングが設置されていても原子炉格納容器内全体
で十分な冷却空調作用を発揮できる原子炉格納容器空調
設備に関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a reactor containment vessel air conditioning system installed in a reactor containment vessel, and relates to a grating for inspecting reactor pressure vessel auxiliary equipment. The present invention relates to a reactor containment vessel air conditioning system that can provide sufficient cooling and air conditioning throughout the reactor containment vessel even if a reactor containment vessel is installed.

(従来の技術) 原子力発電所において原子炉圧力容器を格納して設置さ
れる原子炉格納容器内には、原子炉圧力容器の外にイン
ターナルポンプ、種々の電動機、計装、制御装置、配管
等が多数収納される。そこでこれら収納物の機能が温度
変化によって損なわれないように、原子炉格納容器内に
は原子炉格納容器空調設備も併設される。
(Prior art) Inside the reactor containment vessel installed to house the reactor pressure vessel in a nuclear power plant, there are internal pumps, various electric motors, instrumentation, control devices, and piping outside the reactor pressure vessel. etc. are stored in large numbers. Therefore, in order to prevent the functions of these stored items from being impaired by temperature changes, reactor containment vessel air conditioning equipment is also installed inside the reactor containment vessel.

第3図は、このような原子炉格納容器空調設備1が設置
される原子炉格納容器2の模式図である。
FIG. 3 is a schematic diagram of a reactor containment vessel 2 in which such a reactor containment vessel air conditioning equipment 1 is installed.

まず原子炉格納容器2には、底部に立設されるペデスタ
ル3上に数箇所配管やケーブルを通す開口4を設けて原
子炉遮蔽壁5が延設される。そして、原子炉遮蔽壁5と
この内側に設置される支持スカート6で包囲・支持され
ながら原子炉圧力容器7が格納される。原子炉圧力容器
7の周囲の空間はドライウェル8と呼ばれ、通常はガス
(空気)が充填されるが、冷却材喪失事故の際は気水混
合物が放出される。またドライウェル8は、原子炉圧力
容器7の上部と原子炉遮蔽壁5の上部側面を取巻く上部
ドライウェル8Aと、原子炉遮蔽壁5の下部側面を取巻
き、また原子炉圧力容器7の下方を占める下部ドライウ
ェル8Bに分画される。
First, in the reactor containment vessel 2, a reactor shielding wall 5 is extended by providing openings 4 at several locations on a pedestal 3 that is installed at the bottom to allow pipes and cables to pass through. Then, the reactor pressure vessel 7 is stored while being surrounded and supported by the reactor shielding wall 5 and the support skirt 6 installed inside the reactor shielding wall 5. The space around the reactor pressure vessel 7 is called a dry well 8, and is normally filled with gas (air), but in the event of a loss of coolant accident, a mixture of air and water is released. The dry well 8 also includes an upper dry well 8A that surrounds the upper part of the reactor pressure vessel 7 and the upper side of the reactor shielding wall 5, and an upper drywell 8A that surrounds the lower side of the reactor shielding wall 5 and the lower part of the reactor pressure vessel 7. It is fractionated into the lower dry well 8B.

原子炉格納容器空調設備1は、上部ドライウェル8Aに
設けられる冷却器9とこの冷却器9に接続する送風機1
0およびこの送風機10に接続して上部ドライウェル8
Aおよび下部ドライウェル8Bに延設される冷却ガス送
風ダクト11とを具備する。下部ドライウェル8Bに延
設される冷却ガス送風ダクト11は、前述の開口4付近
で終端する。また冷却器8には、下部ドライウェル7B
内で取り込んだ空気を送る給気ダクト14が接続する。
The reactor containment vessel air conditioning equipment 1 includes a cooler 9 provided in the upper dry well 8A and a blower 1 connected to this cooler 9.
0 and the upper dry well 8 connected to this blower 10.
A and a cooling gas blowing duct 11 extending to the lower dry well 8B. The cooling gas blowing duct 11 extending into the lower dry well 8B terminates near the opening 4 described above. The cooler 8 also includes a lower dry well 7B.
An air supply duct 14 that sends air taken in is connected thereto.

第4図は、第3図における原子炉格納容器空調設備1と
下部ドライウェル7Bの拡大模式図である。第3図と対
応する箇所には同一の符号を付して説明を省略する。
FIG. 4 is an enlarged schematic diagram of the reactor containment vessel air conditioning equipment 1 and the lower dry well 7B in FIG. 3. Portions corresponding to those in FIG. 3 are denoted by the same reference numerals, and explanation thereof will be omitted.

原子炉圧力容器7の底部および支持スカート6の下方に
は複数個のインターナルポンプ12その他の重要な原子
炉圧力容器付属機器(図示せず)が設置されるが、原子
炉遮蔽壁5の開口4の上端内側には、これらの機器を検
査員が点検するときの足場となるグレーティング13が
設置される。
A plurality of internal pumps 12 and other important reactor pressure vessel accessories (not shown) are installed at the bottom of the reactor pressure vessel 7 and below the support skirt 6. A grating 13 is installed inside the upper end of the device 4, which serves as a foothold for inspectors to use when inspecting these devices.

この原子炉格納容器空調設備1においては、冷却器9は
、中に取り入れた空気を冷却し、冷却ガスとして送風機
10に送る。すると送風機10は、この冷却ガスを冷却
ガス送風ダクト11を通じて上部ドライウェル8Aと下
部ドライウェル8Bに送る。その結果、まず上部ドライ
ウェル8Aは特に障害物がないため、この冷却ガスが四
方に行き渡って万遍なく冷却される。
In this reactor containment vessel air conditioning equipment 1, the cooler 9 cools the air taken into it and sends it to the blower 10 as cooling gas. Then, the blower 10 sends this cooling gas to the upper dry well 8A and the lower dry well 8B through the cooling gas blowing duct 11. As a result, since there are no particular obstacles in the upper dry well 8A, this cooling gas is distributed in all directions and is evenly cooled.

他方、下部ドライウェル8Bに送られる冷却ガスは開口
4付近で冷却ガス送風ダクト11から排出されるが、こ
うすると原子炉遮蔽壁5内を冷却する冷却ガスは、原子
炉遮蔽壁5の壁面に沿って流れる旋回流となり、グレー
ティング13下方の原子炉遮蔽壁5内に万遍なく行き渡
って(散乱して)冷却効率が向上する。そして下部ドラ
イウェル8Bが冷却されると、下部ドライウェル8Bに
充填される空気は、給気ダクト11に入り込み冷却器9
に送られる。以後は上述のサイクルが繰返されて原子炉
格納容器2内の空調が保たれる。
On the other hand, the cooling gas sent to the lower dry well 8B is discharged from the cooling gas blowing duct 11 near the opening 4, but in this way, the cooling gas that cools the inside of the reactor shielding wall 5 is discharged from the wall surface of the reactor shielding wall 5. This becomes a swirling flow that flows along the reactor shielding wall 5 below the grating 13 and evenly spreads (is scattered) inside the reactor shielding wall 5, improving cooling efficiency. When the lower dry well 8B is cooled, the air filled in the lower dry well 8B enters the air supply duct 11 and enters the cooler 9.
sent to. Thereafter, the above-described cycle is repeated to maintain air conditioning in the reactor containment vessel 2.

ところで、グレーティング13は、支持スカート6下方
に位置する機器にも冷却ガスが到達するように、例えば
ハニカム形状の格子とする。そして、各格子間の間隔も
、冷却ガスの冷却効果を高める散乱が妨げられないよう
に、検査員の足場を保てる範囲で可能な限り広くする。
By the way, the grating 13 is formed into a honeycomb-shaped grating, for example, so that the cooling gas can reach the equipment located below the support skirt 6. The spacing between each grid is also made as wide as possible within the range that allows the inspector to maintain his or her footing so that the scattering of the cooling gas, which enhances the cooling effect, is not hindered.

しかしこのグレーティング13は、検査員の足場として
の強度を保つ関係上垂直方向に厚みをもたせざるを得な
い。そうすると、冷却ガスは開口4付近からこのグレー
ティング13に傾斜角をなして流入してくるが、この厚
み部分に衝突することによりその流れが静めらる。その
結果、グレーティング13の上方には勢いのない冷却ガ
スしか到達しなくなり、グレーティング13上方の機器
は十分な冷却効果が得られなくなる。
However, the grating 13 must be thick in the vertical direction in order to maintain its strength as a scaffold for the inspector. Then, the cooling gas flows into the grating 13 from the vicinity of the opening 4 at an inclined angle, but the flow is calmed by colliding with this thick portion. As a result, only the cooling gas with low momentum reaches above the grating 13, and the equipment above the grating 13 cannot obtain a sufficient cooling effect.

本発明は上記事情に鑑みてなされたものであり、原子炉
圧力容器付属機器点検用のグレーティングが設置されて
いても原子炉格納容器内全体で十分な冷却空調作用を発
揮できる原子炉格納容器空調設備を提供することを目的
とする。
The present invention has been made in view of the above circumstances, and provides a reactor containment vessel air conditioner that can exert sufficient cooling air conditioning action throughout the reactor containment vessel even if a grating for inspecting reactor pressure vessel auxiliary equipment is installed. The purpose is to provide facilities.

〔発明の構成〕[Structure of the invention]

(課題を解決するための手段) 本発明は上記課題を解決するために、種々の付属機器を
付設した原子炉圧力容器を格納し、かつ前記付属機器点
検用のグレーティングが設置されたドライウェルを有す
る原子炉格納容器内において、原子炉格納容器内のガス
を冷却する冷却器と、この冷却器で冷却されたガスを送
風する送風機と、この送風機に接続し、前記グレーティ
ングの両側に導かれる冷却ガス送風ダクトとを備えて設
けられる原子炉格納容器空調設備を提供する。
(Means for Solving the Problems) In order to solve the above-mentioned problems, the present invention provides a dry well for storing a nuclear reactor pressure vessel equipped with various auxiliary equipment, and in which a grating for inspecting the auxiliary equipment is installed. A cooler for cooling gas in the reactor containment vessel, a blower for blowing the gas cooled by the cooler, and a cooling device connected to the blower and guided to both sides of the grating. Provided is a nuclear reactor containment vessel air conditioning system that is provided with a gas blowing duct.

(作用) 本発明の原子炉格納容器空調設備においては、送風機に
接続する冷却ガス送風ダクトはグレーティングの片側(
下方)で終端するだけでなく、途中で分岐し、グレーテ
ィングを貫通してグレーテインクのもう一方の側(上方
)でも終端する。したがって本発明の原子炉格納容器空
調設備によれば、冷却器で生成される冷却ガスはグレー
ティングの両側に勢いよく噴出され、原子炉格納容器の
全体に万遍なく行き渡る。このため原子炉格納容器は、
内部全体が十分に冷却される。
(Function) In the reactor containment air conditioning system of the present invention, the cooling gas ventilation duct connected to the blower is connected to one side of the grating (
In addition to terminating on the other side (upper side) of the grating ink, it also branches in the middle, passes through the grating, and terminates on the other side (upper side) of the grating ink. Therefore, according to the reactor containment air conditioning system of the present invention, the cooling gas generated by the cooler is vigorously jetted out to both sides of the grating and evenly distributed throughout the reactor containment vessel. For this reason, the reactor containment vessel is
The entire interior is sufficiently cooled.

(実施例) 以下第1図および第2図を参照して本発明の詳細な説明
する。
(Example) The present invention will be described in detail below with reference to FIGS. 1 and 2.

第1図は、付属機器点検用のグレーティング13が設置
される原子炉格納容器下部ドライウェル8Bの断面図で
ある。なお第4図と対応する箇所には同一の符号を付し
て説明を省略する。
FIG. 1 is a sectional view of a lower dry well 8B of the reactor containment vessel in which a grating 13 for inspecting attached equipment is installed. Note that portions corresponding to those in FIG. 4 are designated by the same reference numerals, and description thereof will be omitted.

本実施例に係る原子炉格納容器空調設備20は、冷却ガ
スを生成する冷却器とこの冷却器に接続し冷却ガスを送
風する送風機を備えるが、これらは第3図および第4図
に示した従来の原子炉格納容器空調設備と同様に上部ド
ライウェルに設置されるため、第1図には示されない。
The reactor containment air conditioning equipment 20 according to this embodiment includes a cooler that generates cooling gas and a blower that is connected to the cooler and blows the cooling gas, which are shown in FIGS. 3 and 4. It is not shown in FIG. 1 because it is installed in the upper drywell like conventional reactor containment vessel air conditioning equipment.

また上部ドライウェルは第1図および第2図で説明した
通り、上部ドライウェルに配置される冷却ガス送風ダク
トによって十分に冷却される。
Further, as explained in FIGS. 1 and 2, the upper dry well is sufficiently cooled by the cooling gas blowing duct arranged in the upper dry well.

送風機に接続して下部ドライウェル8Bに延設される冷
却ガス送風ダクト21は、従来と同様、まず一端は開口
4付近、すなわちグレーティング13の下方で第1吹出
口22をもって終端する。
The cooling gas blowing duct 21 connected to the blower and extending into the lower dry well 8B terminates at one end near the opening 4, that is, below the grating 13, with the first outlet 22, as in the conventional case.

しかし本実施例に係る冷却ガス送風ダクト21は原子炉
遮蔽壁5の内側で分岐管23をもって分岐する。そして
この分岐管23は、グレーティング13を貫通し、グレ
ーティング13の上方で第2吹出口24をもって終端す
る。すなわち、本実施例における冷却ガス送風ダクト2
1は、グレーティング13の(両側)上方と下方に導か
れ終端する。
However, the cooling gas blowing duct 21 according to this embodiment branches with a branch pipe 23 inside the reactor shielding wall 5. The branch pipe 23 passes through the grating 13 and terminates above the grating 13 with a second outlet 24 . That is, the cooling gas ventilation duct 2 in this embodiment
1 are guided above and below (on both sides) of the grating 13 and terminate therein.

したがって本実施例の原子炉格納容器空調設備20にお
いては、冷却器で生成され送風機で送られる冷却ガスは
、冷却ガス送風ダクト11を通じて下部ドライウェル8
Bに案内される。そして冷却ガス送風ダクト11を通過
する冷却ガスは、原子炉遮蔽壁5内に入ると、一部が分
岐管23に分岐して流入し、他の一部は第1吹出口24
からグレーティング13の下方に噴出する。この噴出し
た冷却ガスは、原子炉遮蔽壁5の壁面に沿って流れる旋
回流となり、グレーティング13の下方において原子炉
遮蔽壁5内に万遍なく行き渡って冷却作用を発揮する。
Therefore, in the reactor containment air conditioning system 20 of this embodiment, the cooling gas generated by the cooler and sent by the blower passes through the cooling gas blowing duct 11 to the lower dry well 8.
Guided by B. When the cooling gas passing through the cooling gas blowing duct 11 enters the reactor shielding wall 5, part of it branches into the branch pipe 23 and flows into the branch pipe 23, and the other part flows into the first outlet 24.
It is ejected from below the grating 13. The ejected cooling gas becomes a swirling flow that flows along the wall surface of the reactor shielding wall 5, and evenly spreads within the reactor shielding wall 5 below the grating 13, exerting a cooling effect.

他方、分岐管23に分岐した冷却ガスは、分岐管23内
を通過しながら原子炉遮蔽壁5内を上方に進み、第2吹
出口24からグレーティング13の上方に噴出する。そ
してこの噴出した冷却ガスは勢いがあるため、グレーテ
ィング13と支持スカート6に挟まれた空間を隅々まで
行き渡り、この空間内に配置されたインタータナルボン
プ12外様々の原子炉圧力容器7付属機器(図示せず)
を十分に冷却する。
On the other hand, the cooling gas branched into the branch pipe 23 travels upward within the reactor shielding wall 5 while passing through the branch pipe 23 and is ejected above the grating 13 from the second outlet 24 . Since the ejected cooling gas has a strong force, it spreads to every corner of the space between the grating 13 and the support skirt 6, and the internal bomb 12 and various auxiliary equipment of the reactor pressure vessel 7 disposed within this space. (not shown)
Cool thoroughly.

第2図は本実施例の原子炉格納容器空調設備20を用い
て下部ドライウェル8Bを冷却した結果を従来の原子炉
格納容器空調設備による冷却と比較して示した図である
。同図中破線は本実施例による下部ドライウェル8B内
の温度を示し、実線は従来の原子炉格納容器空調設備で
冷却した場合(比較例)の温度を示す。この図から分か
るように、グレーティングの下方においては、本実施例
による冷却も比較例の冷却も同様な効果を奏し、温度は
互いにほぼ同じである。
FIG. 2 is a diagram showing the results of cooling the lower dry well 8B using the reactor containment vessel air conditioning system 20 of this embodiment in comparison with cooling by the conventional reactor containment vessel air conditioning system. In the figure, the broken line indicates the temperature in the lower dry well 8B according to the present embodiment, and the solid line indicates the temperature when cooling is performed using a conventional reactor containment vessel air conditioning system (comparative example). As can be seen from this figure, below the grating, the cooling according to this embodiment and the cooling according to the comparative example have similar effects, and the temperatures are almost the same.

しかしグレーティングの上方においては、従来の原子炉
格納容器空調設備を用いた場合は、勢いのある冷却ガス
がグレーティングを通過できないため十分な冷却効果が
得られず高温となり、ブレティングを境にして温度が不
連続になっている。
However, above the grating, when conventional reactor containment air conditioning equipment is used, the powerful cooling gas cannot pass through the grating, so a sufficient cooling effect cannot be obtained and the temperature rises. is discontinuous.

とこらが本実施例においてはグレーティングの上方でも
十分な冷却が行われ、比較例に比べて温度が大幅に低く
グレーティングの上方と下方で温度が連続している。
However, in this example, sufficient cooling is performed even above the grating, and the temperature is significantly lower than that of the comparative example, and the temperature is continuous above and below the grating.

したがって本実施例の原子炉格納容器空調設備20によ
れば、上部ドライウェルは勿論のこと下部ドライウェル
8Bも、グレーティング13の上方と下方を問わず十分
に冷却される。
Therefore, according to the reactor containment air conditioning system 20 of this embodiment, not only the upper dry well but also the lower dry well 8B are sufficiently cooled regardless of whether they are above or below the grating 13.

〔発明の効果〕〔Effect of the invention〕

以上説明したように、本発明の原子炉格納容器空調設備
においては、送風機に接続する冷却ガス送風ダクトはグ
レーティングの片側(下方)で終端するだけでなく、途
中で分岐し、グレーティングを貫通してグレーティング
のもう一方の側(上方)でも終端する。したがって本発
明の原子炉格納容器空調設備によれば、冷却器で生成さ
れる冷却ガスはグレーティングの両側に勢いよく噴出さ
れ、原子炉格納容器の全体に万遍なく行き渡る。このた
め原子炉格納容器は、内部全体が十分に冷却される。
As explained above, in the reactor containment air conditioning system of the present invention, the cooling gas blowing duct connected to the blower not only terminates on one side (below) of the grating, but also branches in the middle and passes through the grating. It also terminates on the other side (above) of the grating. Therefore, according to the reactor containment air conditioning system of the present invention, the cooling gas generated by the cooler is vigorously jetted out to both sides of the grating and evenly distributed throughout the reactor containment vessel. Therefore, the entire inside of the reactor containment vessel is sufficiently cooled.

・・・送風機、13・・・グレーティング、21・・・
冷却ガス送風ダクト、23・・・分岐管。
...Blower, 13...Grating, 21...
Cooling gas ventilation duct, 23...branch pipe.

Claims (1)

【特許請求の範囲】[Claims] 種々の付属機器を付設した原子炉圧力容器を格納し、か
つ前記付属機器点検用のグレーティングが設置されたド
ライウェルを有する原子炉格納容器内において、原子炉
格納容器内のガスを冷却する冷却器と、この冷却器で冷
却されたガスを送風する送風機と、この送風機に接続し
、前記グレーティングの両開口側に導かれる冷却ガス送
風ダクトとを備えて設けられる原子炉格納容器空調設備
A cooler for cooling gas in the reactor containment vessel, which stores a reactor pressure vessel equipped with various auxiliary equipment and has a dry well in which a grating for inspecting the auxiliary equipment is installed. Reactor containment vessel air conditioning equipment is provided with: a blower for blowing gas cooled by the cooler; and a cooling gas blowing duct connected to the blower and guided to both opening sides of the grating.
JP1331010A 1989-12-22 1989-12-22 Nuclear reactor containment air conditioning facility Pending JPH03194499A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1331010A JPH03194499A (en) 1989-12-22 1989-12-22 Nuclear reactor containment air conditioning facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1331010A JPH03194499A (en) 1989-12-22 1989-12-22 Nuclear reactor containment air conditioning facility

Publications (1)

Publication Number Publication Date
JPH03194499A true JPH03194499A (en) 1991-08-26

Family

ID=18238815

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1331010A Pending JPH03194499A (en) 1989-12-22 1989-12-22 Nuclear reactor containment air conditioning facility

Country Status (1)

Country Link
JP (1) JPH03194499A (en)

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