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JPH0636062B2 - Cooling device in the reactor containment vessel - Google Patents
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JPH0636062B2 - Cooling device in the reactor containment vessel - Google Patents

Cooling device in the reactor containment vessel

Info

Publication number
JPH0636062B2
JPH0636062B2 JP63285769A JP28576988A JPH0636062B2 JP H0636062 B2 JPH0636062 B2 JP H0636062B2 JP 63285769 A JP63285769 A JP 63285769A JP 28576988 A JP28576988 A JP 28576988A JP H0636062 B2 JPH0636062 B2 JP H0636062B2
Authority
JP
Japan
Prior art keywords
containment vessel
reactor containment
shielding wall
air
pressure 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.)
Expired - Lifetime
Application number
JP63285769A
Other languages
Japanese (ja)
Other versions
JPH02132400A (en
Inventor
文高 河野
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 Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
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 Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP63285769A priority Critical patent/JPH0636062B2/en
Publication of JPH02132400A publication Critical patent/JPH02132400A/en
Publication of JPH0636062B2 publication Critical patent/JPH0636062B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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)
  • Drying Of Gases (AREA)

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は原子力発電所における原子炉格納容器内の冷却
装置に関する。
DETAILED DESCRIPTION OF THE INVENTION Object of the Invention (Field of Industrial Application) The present invention relates to a cooling device for a reactor containment vessel in a nuclear power plant.

(従来の技術) 従来、原子力発電所等の原子力発電所等の原子力プラン
トにおける原子炉格納容器内は第2図の要部断面図で示
すように中央に原子炉圧力容器1をペデスタル2上に設
置し、その周囲に原子炉圧力容器1からの放射線及び熱
を遮断する目的で円筒状遮蔽壁3が設置されている。原
子炉圧力容器1および遮蔽壁3の全体を覆って設けた原
子炉格納容器4内をドライウェルとして原子炉運転のた
めの各種機器を設置している。この中で特に原子炉圧力
容器1と遮蔽壁3との空間部5は原子炉圧力容器1の放
熱により高温エリアとなる。そこで、遮蔽壁3の下部に
環状の給気ノズル6を配設し、遮蔽壁3を貫通させた給
気ダクト7を介してローカルクーラ8から冷風を供給
し、前記空間部5内の原子炉圧力容器1の外周に沿って
略均等に吹き出させて冷却を行っている。この冷風は原
子炉圧力容器1の外周に沿って空間部5内を冷却し、上
昇して遮蔽壁3の最上部から流出拡散して原子炉格納容
器4内を経由し、原子炉格納容器4内の雰囲気と一緒に
なって前記ローカルクーラ8の吸入口8a に吸込まれて
再び冷却される。
(Prior Art) Conventionally, in a nuclear reactor containment vessel in a nuclear power plant such as a nuclear power plant, a reactor pressure vessel 1 is placed in the center on a pedestal 2 as shown in a sectional view of a main part of FIG. The cylindrical shielding wall 3 is installed around the same for the purpose of blocking radiation and heat from the reactor pressure vessel 1. Various devices for operating the reactor are installed by using the inside of the reactor containment vessel 4 which covers the entire reactor pressure vessel 1 and the shielding wall 3 as a dry well. In particular, the space 5 between the reactor pressure vessel 1 and the shield wall 3 becomes a high temperature area due to heat radiation from the reactor pressure vessel 1. Therefore, an annular air supply nozzle 6 is arranged below the shielding wall 3, and cold air is supplied from a local cooler 8 via an air supply duct 7 penetrating the shielding wall 3 to provide a reactor in the space 5. The pressure vessel 1 is blown out substantially uniformly along the outer periphery of the pressure vessel 1 for cooling. This cold air cools the space 5 along the outer periphery of the reactor pressure vessel 1, rises, flows out from the uppermost portion of the shielding wall 3, diffuses, passes through the reactor containment vessel 4, and passes through the reactor containment vessel 4 Together with the atmosphere inside, it is sucked into the suction port 8a of the local cooler 8 and cooled again.

また、原子炉格納容器内結露防止のための除湿器11を原
子炉格納容器4内のドライウェルに設置して除湿冷却し
ている。
Further, a dehumidifier 11 for preventing dew condensation in the reactor containment vessel is installed in a dry well in the reactor containment vessel 4 for dehumidification cooling.

(発明が解決しようとする課題) 原子炉圧力容器1と遮蔽壁3との空間部5は縦長のた
め、遮蔽壁3の最下部から給気された冷風が遮蔽壁3の
最上部に到達するまでに大幅に温度が上昇して、最上部
付近では冷却効果が低下する。また遮蔽壁3には原子炉
圧力容器1に接続された種々のノズル9が貫通してお
り、この部分は定期的に検査をするための開口10が設け
られている。このため、冷風がこれら開口10,ノズル9
の間隙から遮蔽壁3外へ流出することもあって、遮蔽壁
3の最上部まで冷風が十分に到達しないという課題があ
った。また遮蔽壁3の上部付近では高温となった空気が
滞留してローカルクーラ8が設置されている原子炉格納
容器4の下部との温度差が大きくなり、ドライウェルの
温度の均等化が困難になる課題があった。
(Problems to be Solved by the Invention) Since the space portion 5 between the reactor pressure vessel 1 and the shielding wall 3 is vertically long, the cold air supplied from the lowermost portion of the shielding wall 3 reaches the uppermost portion of the shielding wall 3. By the time the temperature rises significantly, the cooling effect decreases near the top. Further, various nozzles 9 connected to the reactor pressure vessel 1 penetrate through the shielding wall 3, and an opening 10 is provided in this portion for periodical inspection. For this reason, the cold air is blown by these openings 10 and nozzles 9.
There is also a problem that the cold air does not reach the uppermost part of the shielding wall 3 sufficiently because it may flow out of the shielding wall 3 through the gap. Further, in the vicinity of the upper part of the shielding wall 3, hot air stays and the temperature difference with the lower part of the reactor containment vessel 4 in which the local cooler 8 is installed becomes large, making it difficult to equalize the temperature of the dry well. There was a problem that became.

本発明は上記課題を解決するためになされたもので、原
子炉圧力容器1と遮蔽壁3との間の空間部5及び原子炉
格納容器ベローシール部周辺の高温エリアの熱除去を効
率的に実施して遮蔽壁の上部付近に高温部が生じないよ
うに、かつ原子炉格納容器内における上部と下部の温度
分布を適正になし得る原子炉格納容器内の冷却装置を提
供することにある。
The present invention has been made to solve the above problems, and efficiently removes heat in the high temperature area around the space 5 between the reactor pressure vessel 1 and the shield wall 3 and the bellow seal portion of the containment vessel. It is an object of the present invention to provide a cooling device in a reactor containment vessel, which can be implemented so that a high temperature part does not occur near the upper part of the shielding wall, and the temperature distribution of the upper part and the lower part in the reactor containment vessel can be appropriately adjusted.

[発明の構成] (課題を解決するための手段) 本発明は原子炉格納容器内のドライウェルに設置された
ローカルクーラに結露防止用除湿器を接続し、この除湿
器で冷却した冷風を前記ドライウェルの高温エリアに吹
き出す給気ダクトを接続してなることを特徴とする。
[Structure of the Invention] (Means for Solving the Problems) In the present invention, a dehumidifier for preventing dew condensation is connected to a local cooler installed in a drywell in a reactor containment vessel, and cold air cooled by the dehumidifier is used as described above. It is characterized by connecting an air supply duct blowing out to a high temperature area of the dry well.

(作 用) 発熱源である原子炉圧力容器と、その熱遮蔽体である遮
蔽壁の空間部にローカルクーラで冷却した空気を除湿器
でさらに冷却してその冷風を給気ダクトから吹き出して
冷却を行う。従って、空間部における風量が削減できま
た温度上昇が低くなり、冷却効果が得られる。特に遮蔽
壁の熱応力が低下する。
(Operation) Air cooled by the local cooler is further cooled by the dehumidifier in the space of the reactor pressure vessel, which is the heat source, and the shielding wall, which is the heat shield, and the cold air is blown from the air supply duct to cool it. I do. Therefore, the air volume in the space can be reduced, the temperature rise can be reduced, and the cooling effect can be obtained. Especially, the thermal stress of the shielding wall is reduced.

また、同様に遮蔽壁の上部付近にも除湿器からの冷風を
吹き出して高温空気滞留を軽減してドライウェルにおけ
る温度の均等化をはかることができる。
Similarly, cold air from the dehumidifier can be blown out near the upper part of the shielding wall to reduce the retention of high-temperature air and equalize the temperature in the dry well.

(実施例) 本発明の一実施例を第1図を参照して説明する。なお、
前述した従来技術と同一の構成部分には同一符号を付し
て詳細な説明は省略する。
(Embodiment) An embodiment of the present invention will be described with reference to FIG. In addition,
The same components as those of the above-mentioned conventional technique are designated by the same reference numerals, and detailed description thereof will be omitted.

第1図は原子炉格納容器内の要部断面図で、中央でペデ
スタル2に設置した原子炉圧力容器1とこれの周囲に円
筒状の遮蔽壁3を設ける。
FIG. 1 is a cross-sectional view of a main part of the reactor containment vessel, in which a reactor pressure vessel 1 installed in a pedestal 2 at the center and a cylindrical shield wall 3 are provided around the reactor pressure vessel 1.

原子炉圧力容器1と遮蔽壁3との空間5の最下部に環状
で冷気を吹出す給気ノズル12a を設置し給気ダクト7を
接続してローカルクーラ8から冷風を供給する。
At the bottom of the space 5 between the reactor pressure vessel 1 and the shielding wall 3, an annular air supply nozzle 12a for blowing cold air is installed, and an air supply duct 7 is connected to supply cold air from a local cooler 8.

給気ダクト7の途中に除湿器11を設置し、前記ローカル
クーラ8で冷却された空気を除湿器11でさらに冷却して
供給する。
A dehumidifier 11 is installed in the middle of the air supply duct 7, and the air cooled by the local cooler 8 is further cooled by the dehumidifier 11 and supplied.

同様に原子炉圧力容器1と遮蔽壁との空間5を通過した
空気がドライウェル空間に吹き出される遮蔽壁3の上部
エリアにもローカルクーラ8及び除湿器11で冷却された
空気を給気ダクト7b を環状に配置し、給気ノズル12b
から吹き出す構成とする。
Similarly, the air cooled by the local cooler 8 and the dehumidifier 11 is also supplied to the upper area of the shield wall 3 where the air passing through the space 5 between the reactor pressure vessel 1 and the shield wall is blown into the drywell space. 7b are arranged in an annular shape, and the air supply nozzle 12b
It will be blown out from.

次に上記構成による作用について述べる。Next, the operation of the above configuration will be described.

ドライウェル空間の空気はローカルクーラ8で循環冷却
されるが、ローカルクーラ8で冷却した空気を除湿器11
でさらに冷却して冷風として給気ダクト7を通して給気
ノズル12a から原子炉圧力容器1と遮蔽壁3の間の空間
5に供給する。除湿器11によって冷却され温度が低くな
り、空間5への供給量を削減できるので遮蔽壁3内側の
圧力が小さくなり、原子炉圧力容器1保温材への漏洩及
び開口10からの冷風の流出が少なく、冷却効率が上昇す
る。温度上昇も小さくなり、冷却効果が大となる。
The air in the drywell space is circulated and cooled by the local cooler 8, but the air cooled by the local cooler 8 is removed by the dehumidifier 11
Is further cooled and supplied as cold air from the air supply nozzle 12a through the air supply duct 7 to the space 5 between the reactor pressure vessel 1 and the shield wall 3. Since the temperature is lowered by the dehumidifier 11 and the supply amount to the space 5 can be reduced, the pressure inside the shielding wall 3 becomes small, and the leakage to the heat insulating material of the reactor pressure vessel 1 and the outflow of cold air from the opening 10 occur. The cooling efficiency is increased. The temperature rise is also small and the cooling effect is large.

空間部5を流れて高温となった空気は遮蔽壁3の上部か
らドライウェルの上部空間に吹き出され高温エリアとな
る。この高温エリアにはドライウェルの上方に設置した
ローカルクーラ8および除湿器11を流れて冷却された冷
風が給気ノズル12b から吹き出されて拡散し冷却され
る。このようにしてドライウェルの高温エリアに高温空
気が滞留することを防止することが可能となる。
The air that has flowed through the space 5 and has a high temperature is blown out from the upper portion of the shielding wall 3 into the upper space of the dry well, and becomes a high temperature area. In this high temperature area, the cold air that has flowed through the local cooler 8 and the dehumidifier 11 installed above the dry well and is cooled is blown out from the air supply nozzle 12b and diffused and cooled. In this way, it becomes possible to prevent high temperature air from staying in the high temperature area of the dry well.

[発明の効果] 本発明によれば、原子炉圧力容器及び遮蔽壁の冷却効果
が向上するので、熱応力が低減され劣化が防止できる。
また原子炉圧力容器と遮蔽壁との空間部の冷却空気の温
度上昇も低く、高温エリアの高温空気が原子炉格納容器
内に拡散しないのでドライウェルにおける温度の均等化
とこれにより冷却装置の小型化が可能となる効果があ
る。
[Advantages of the Invention] According to the present invention, the cooling effect of the reactor pressure vessel and the shielding wall is improved, so that thermal stress is reduced and deterioration can be prevented.
Also, the temperature rise of the cooling air in the space between the reactor pressure vessel and the shielding wall is low, and the high temperature air in the high temperature area does not diffuse into the reactor containment vessel, so the temperature in the dry well is equalized and the cooling device is made smaller. There is an effect that can be realized.

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

第1図は本発明の一実施例の原子炉格納容器内の要部断
面図、第2図は従来の原子炉格納容器内の要部断面図で
ある。 1……原子炉圧力容器 3……遮蔽壁 4……原子炉格納容器 5……空間部 7,7a ,7b ……給気ダクト 8……ローカルクーラ 8a……吸入口 9……ノズル 10……開口 11……除湿器 12a,12b……給気ノズル
FIG. 1 is a cross-sectional view of a main part in a reactor containment vessel according to an embodiment of the present invention, and FIG. 2 is a cross-sectional view of a main part in a conventional reactor containment vessel. 1 ... Reactor pressure vessel 3 ... Shielding wall 4 ... Reactor containment vessel 5 ... Space section 7, 7a, 7b ... Air supply duct 8 ... Local cooler 8a ... Suction port 9 ... Nozzle 10 ... … Aperture 11 …… Dehumidifier 12a, 12b …… Air supply nozzle

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】原子炉格納容器内のドライウェルに設置さ
れたローカルクーラに結露防止用除湿器を接続し、この
除湿器で冷却した冷風を前記ドライウェルの高温エリア
に吹き出す給気ダクトを接続してなることを特徴とする
原子炉格納容器内の冷却装置。
1. A dehumidifier for preventing dew condensation is connected to a local cooler installed in a drywell in a reactor containment vessel, and an air supply duct for blowing cold air cooled by the dehumidifier to a high temperature area of the drywell is connected. A cooling device in a reactor containment vessel characterized by the following.
JP63285769A 1988-11-14 1988-11-14 Cooling device in the reactor containment vessel Expired - Lifetime JPH0636062B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63285769A JPH0636062B2 (en) 1988-11-14 1988-11-14 Cooling device in the reactor containment vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63285769A JPH0636062B2 (en) 1988-11-14 1988-11-14 Cooling device in the reactor containment vessel

Publications (2)

Publication Number Publication Date
JPH02132400A JPH02132400A (en) 1990-05-21
JPH0636062B2 true JPH0636062B2 (en) 1994-05-11

Family

ID=17695817

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63285769A Expired - Lifetime JPH0636062B2 (en) 1988-11-14 1988-11-14 Cooling device in the reactor containment vessel

Country Status (1)

Country Link
JP (1) JPH0636062B2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2818628B2 (en) * 1991-02-25 1998-10-30 富士写真フイルム株式会社 Data recording method in memory card and memory card system

Also Published As

Publication number Publication date
JPH02132400A (en) 1990-05-21

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