JPS5987393A - Device for controlling humidity in reactor container - Google Patents

Device for controlling humidity in reactor container

Info

Publication number
JPS5987393A
JPS5987393A JP57195978A JP19597882A JPS5987393A JP S5987393 A JPS5987393 A JP S5987393A JP 57195978 A JP57195978 A JP 57195978A JP 19597882 A JP19597882 A JP 19597882A JP S5987393 A JPS5987393 A JP S5987393A
Authority
JP
Japan
Prior art keywords
containment vessel
reactor containment
lid
gas
humidity
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
JP57195978A
Other languages
Japanese (ja)
Inventor
元浩 会沢
大角 克己
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.)
Hitachi Ltd
Hitachi Industry and Control Solutions Co Ltd
Original Assignee
Hitachi Engineering Co Ltd Ibaraki
Hitachi Ltd
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 Hitachi Engineering Co Ltd Ibaraki, Hitachi Ltd filed Critical Hitachi Engineering Co Ltd Ibaraki
Priority to JP57195978A priority Critical patent/JPS5987393A/en
Publication of JPS5987393A publication Critical patent/JPS5987393A/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

  • Control Of Non-Electrical Variables (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の利用分野〕 本発明は、原子炉格納容器内の湿度コントロール装置に
係り、圧力抑制水内の潜ったガスが原子炉格納ga内に
移動すること全抑制するに好適なガス拡散防止装置に関
する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a humidity control device in a reactor containment vessel, which completely suppresses the movement of gas trapped in pressure suppression water into the reactor containment vessel. The present invention relates to a gas diffusion prevention device suitable for.

〔従来技術〕[Prior art]

原子炉格納容器内のガスの温度コントロールシステムを
第1図によって説明する。第1図において原子炉格納容
61内は原子炉の運転中、事故時に発生する水素による
爆発を防止するために窒素ガスを密封しである。窒素ガ
スの温度コントロールはドライウェル冷却器に原子炉格
納容器1の上層および中層部のガスを吸気ダクト3から
導き冷却をした後排気ダクト4から排出されている。原
子炉格納容器1内および吸気ダクト3内のガスの温度は
約70Cであり、冷却器2で冷却されて排出される排気
口付近の温度は約30C″C″あり、さらに、原子炉格
納容器中央部の排気口5の上方に通っている制御棒駆動
水配管には常に冷却水が流れているため配管表面温度は
10〜40Cの範囲にあるため冷却器2によって冷却さ
れ相対湿度が上昇しているガスが制伸棒駆励配管に吹き
つけられることによってさらに冷却され、露結する場合
がある。さらに配管表面に生成した水滴にガス中に含ま
れる塩素が溶は込みm縮される。
A gas temperature control system within the reactor containment vessel will be explained with reference to FIG. In FIG. 1, the inside of a reactor containment vessel 61 is sealed with nitrogen gas during operation of the reactor to prevent an explosion due to hydrogen that would occur in the event of an accident. The temperature of the nitrogen gas is controlled by introducing the gas from the upper and middle layers of the reactor containment vessel 1 into the dry well cooler through the intake duct 3, cooling it, and then exhausting it through the exhaust duct 4. The temperature of the gas inside the reactor containment vessel 1 and the intake duct 3 is about 70C, and the temperature near the exhaust port where it is cooled by the cooler 2 and discharged is about 30C''C''. Cooling water is always flowing through the control rod drive water pipe that runs above the central exhaust port 5, so the pipe surface temperature is in the range of 10 to 40C, so it is cooled by the cooler 2 and the relative humidity increases. When the gas is blown onto the restraint rod drive piping, it may be further cooled and may form condensation. Furthermore, chlorine contained in the gas dissolves in water droplets generated on the surface of the pipe and causes condensation.

このようにして発生した高塩素濃度の水滴が存在する場
所は腐食が優先的に進み配管破断に紋る起点となる。
Locations where water droplets with a high chlorine concentration are present are where corrosion preferentially progresses and becomes a starting point for pipe rupture.

以上のような配管表面に水滴が発生することによって起
る配管破面の対策としては、原子炉格納容器内の湿度を
下げることが最も有効でるる。従って新たに、冷却器2
に採用している冷却水の塩度を、冷凍機を用いてさらに
低くシ、冷却器に除湿機能を持たせて運転されている。
The most effective measure against pipe fractures caused by water droplets on the pipe surface is to lower the humidity inside the reactor containment vessel. Therefore, a new cooler 2
The salinity of the cooling water used in the system is lowered by using a refrigerator, and the cooler is equipped with a dehumidifying function.

しかし、原子炉格納容器lの底部の開口部から圧力抑制
室7内のプール水8の蒸発によって高湿となったガスが
常時拡散してくるため、十分な湿度低下が実施できない
という問題かめる。
However, since gas that has become highly humid due to evaporation of the pool water 8 in the pressure suppression chamber 7 constantly diffuses from the opening at the bottom of the reactor containment vessel 1, a problem arises in that sufficient humidity cannot be lowered.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、原子炉格納容器内の湿度コントロール
を完全にするために、原子炉の運転中は圧力抑制室内の
高湿ガス全遮蔽する装置を提供することにある。
SUMMARY OF THE INVENTION An object of the present invention is to provide a device that completely shields high-humidity gas in a pressure suppression chamber during operation of a nuclear reactor in order to completely control humidity in a reactor containment vessel.

〔発明の概要〕[Summary of the invention]

原子炉格納容器内の低温配管の破断は、格納容器内の湿
度が商いために配管表面に水滴ができ、その水滴にガス
中の塩化物が溶は込むために腐食が促進されることによ
る。
The rupture of low-temperature piping inside the reactor containment vessel is due to water droplets forming on the piping surface due to low humidity in the containment vessel, and chlorides in the gas dissolving into the water droplets, accelerating corrosion.

従って配管破断の対重としては、原子炉格納容器内の湿
度?低くコノトロールすることによって、露結をなくし
、腐食の発生全抑制することが有効であると考えた。
Therefore, the relative weight of pipe rupture is the humidity inside the reactor containment vessel? We believe that it is effective to eliminate dew condensation and completely suppress the occurrence of corrosion by controlling the control at a low level.

〔発明の実施例〕[Embodiments of the invention]

以下、本発明の一実施例を第2図によって説明する。 An embodiment of the present invention will be described below with reference to FIG.

圧力抑制室内の高湿なガスの拡散を遮蔽するために第2
図(1)に示すような開口部に盆わせた蓋ioi付ける
A second
Attach a tray lid to the opening as shown in Figure (1).

この蓋10は、原子炉格納容器1内に窒素ガス全封入す
る際、圧力抑制室内窒素ガス封入口から開口部9を通っ
て原子炉格納容器1に流入する窒素ガスを通さなければ
ならないため、第2図(2)に示すように、蓋lOが上
下する開閉装[11を有するものである。
When the reactor containment vessel 1 is completely filled with nitrogen gas, this lid 10 must pass the nitrogen gas flowing into the reactor containment vessel 1 from the nitrogen gas filling port in the pressure suppression chamber through the opening 9. As shown in FIG. 2 (2), the lid 1O has an opening/closing device [11] that moves up and down.

また、圧力抑制室プール水は事故時に発生したガス全吸
収することおよび炉水喪失事故時の補給水として貯えら
れているものである。特に、前者の事故時に原子炉格納
容器内に発生したガスを吸収さ、ぜるために、以下の2
つの機能のうちいずれか一方あるいは両者の機能を有し
ている。
In addition, the pressure suppression chamber pool water is stored to absorb all the gas generated during an accident and as make-up water in the event of a loss of reactor water accident. In particular, in order to absorb and eliminate the gas generated in the reactor containment vessel during the former accident, the following two
It has one or both of the following functions.

第一に、第2図(1)に示すように圧力抑制室と、原子
炉格納容器の圧力差が0.1気圧で破れる膜12を張る
。例えばガラス、プラスチック等で熱によって変形しに
くいものt運ぶ。
First, as shown in FIG. 2 (1), a membrane 12 is installed that can rupture at a pressure difference of 0.1 atmosphere between the pressure suppression chamber and the reactor containment vessel. For example, transport items such as glass and plastic that are difficult to deform due to heat.

第二は、第3図に示すようVC圧力抑制室および原子炉
格納容器の圧力計13の信号を制御装置14で判断しO
11気圧以上で蓋10を開く信号全ケーブル15によっ
て送るシステムでるる。
Second, as shown in FIG.
There is a system in which a signal is sent by all cables 15 to open the lid 10 at 11 atmospheres or more.

ま7′c蓋10の開閉はW、4図に示すように、モータ
16によって歯車17が回転することによって回転子1
8が回転し、支柱19を上下するシステムとし、蓋10
を開閉させる。原子炉起動時の窒素ガス封入の際の開お
よび運転中の閉は原子炉格納容器外で操作し、圧力抑制
室内と原子炉格納容器内との圧力差0.1気圧以上での
開は自動制御とする。
7'c The lid 10 is opened and closed by W. As shown in FIG.
8 rotates to move the support column 19 up and down, and the lid 10
open and close. Opening when charging nitrogen gas at reactor startup and closing during operation are operated outside the reactor containment vessel, and it is automatically opened when the pressure difference between the pressure suppression chamber and the reactor containment vessel is 0.1 atmosphere or more. Control.

〔発明の効果〕〔Effect of the invention〕

以上のシステムによって、原子炉格納容器内の湿度コン
トロールが容易となり、除湿用の冷凍機の設備も小さく
することができる。
With the above system, it becomes easy to control the humidity inside the reactor containment vessel, and the dehumidifying refrigerator equipment can also be made smaller.

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

第1図は原子炉格納容器内のガスの流れおよびガスの温
度コントロールを説明する図、第2図は圧力抑制室内の
高湿のガスを遮蔽する蓋の構造および作動を説明する図
、第3図は圧力抑制室と原子炉格納容器内との圧力差を
検出して蓋を開にするシステムを説明する図、第4図は
圧力抑制室高湿ガス趨蔽用蓋の作動を説明する図である
。 1・・・原子炉格納容器、2・・・冷却器、3・・・吸
気ダクト、4・・・排気ダクト、5・・・排気口、6・
・・制−Il14I44!駆動水配管、7・・・圧力抑
制室、8・・・圧力抑制室プール水、9・・・開口部、
10・・・圧力抑制室高湿ガス遮蔽用蓋、11・・・蓋
開閉装置、12・・・圧力抑制室用圧力計、13・・・
原子炉格納容器用圧力計、14・・・蓋m+制御装置、
15・・・蓋制御信号送信ケーブル、16・・・蓋部動
用モータ、17・・・歯車、18・・・回転111図 第2図 竿3 口
Figure 1 is a diagram explaining the gas flow and gas temperature control in the reactor containment vessel, Figure 2 is a diagram explaining the structure and operation of the lid that shields high humidity gas in the pressure suppression chamber, and Figure 3 The figure illustrates a system that detects the pressure difference between the pressure suppression chamber and the inside of the reactor containment vessel and opens the lid. Figure 4 illustrates the operation of the pressure suppression chamber high-humidity gas cover. It is. DESCRIPTION OF SYMBOLS 1... Reactor containment vessel, 2... Cooler, 3... Intake duct, 4... Exhaust duct, 5... Exhaust port, 6...
... System-Il14I44! Drive water piping, 7... Pressure suppression chamber, 8... Pressure suppression chamber pool water, 9... Opening,
10... Pressure suppression chamber high humidity gas shielding lid, 11... Lid opening/closing device, 12... Pressure suppression chamber pressure gauge, 13...
Reactor containment vessel pressure gauge, 14...lid m+control device,
15... Lid control signal transmission cable, 16... Lid movement motor, 17... Gear, 18... Rotation 111 Figure 2 Rod 3 Mouth

Claims (1)

【特許請求の範囲】 1゜原子炉格納容器内の湿度コントロールシステムの一
部として、原子炉格納容器の圧力抑制開口部に蓋を設置
すること′jk特徴とする原子炉格納容器内湿度コント
ロール装置。 2、特許請求の範囲第1項において、原子炉格納容器内
ガスの置換時に開口部を開閉できる装置を有すること全
特徴とする原子炉格納容器内湿度コントロール装置。 3、%許請ボの範囲第1項において、原子炉格納容器内
と圧力抑制室内の圧力差が0.1気圧以上で蓋が開くシ
ステム分有すること全特徴とする原子炉格納容器内湿度
コントロール装置。 4、%許屑求の範囲第1項において、原子炉格納容器内
と圧力抑制室内の圧力差が0.1気圧以上で破れる膜を
■することを特徴とする原子炉格納容器内湿度コントロ
ール製置。
[Claims] 1. A humidity control device in a reactor containment vessel, characterized in that a lid is installed at a pressure suppression opening of the reactor containment vessel as part of a humidity control system in the reactor containment vessel. . 2. The humidity control device in a reactor containment vessel according to claim 1, which is characterized by having a device that can open and close an opening when replacing gas in the reactor containment vessel. 3. Scope of Permit Request In Clause 1, humidity control inside the reactor containment vessel is characterized by having a system that opens the lid when the pressure difference between the reactor containment vessel and the pressure suppression chamber is 0.1 atmosphere or more. Device. 4. Range of Permissible Waste Requirement In Item 1, the product is manufactured by a humidity controller in the reactor containment vessel characterized by having a membrane that ruptures when the pressure difference between the reactor containment vessel and the pressure suppression chamber is 0.1 atm or more. Place.
JP57195978A 1982-11-10 1982-11-10 Device for controlling humidity in reactor container Pending JPS5987393A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57195978A JPS5987393A (en) 1982-11-10 1982-11-10 Device for controlling humidity in reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57195978A JPS5987393A (en) 1982-11-10 1982-11-10 Device for controlling humidity in reactor container

Publications (1)

Publication Number Publication Date
JPS5987393A true JPS5987393A (en) 1984-05-19

Family

ID=16350165

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57195978A Pending JPS5987393A (en) 1982-11-10 1982-11-10 Device for controlling humidity in reactor container

Country Status (1)

Country Link
JP (1) JPS5987393A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60228474A (en) * 1984-04-27 1985-11-13 Neos Co Ltd 2-(4'-perfluoroalkenyloxyphenyl)-4-isopropyl-5,5-dimethyl-1,3-dioxane and 2-alkyl-substitution product and preparation thereof

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60228474A (en) * 1984-04-27 1985-11-13 Neos Co Ltd 2-(4'-perfluoroalkenyloxyphenyl)-4-isopropyl-5,5-dimethyl-1,3-dioxane and 2-alkyl-substitution product and preparation thereof

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