JPH02253193A - Vent system for steam condenser - Google Patents
Vent system for steam condenserInfo
- Publication number
- JPH02253193A JPH02253193A JP1073927A JP7392789A JPH02253193A JP H02253193 A JPH02253193 A JP H02253193A JP 1073927 A JP1073927 A JP 1073927A JP 7392789 A JP7392789 A JP 7392789A JP H02253193 A JPH02253193 A JP H02253193A
- Authority
- JP
- Japan
- Prior art keywords
- steam
- nitrogen
- remote control
- control valve
- condenser
- 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
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
(産業上の利用分野)
本発明は冷却材喪失事故時の原子炉圧力容器からの蒸気
を凝縮させる蒸気凝縮装置のベントシステムに関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Field of Application) The present invention relates to a vent system for a steam condenser that condenses steam from a nuclear reactor pressure vessel during a loss of coolant accident.
(従来の技術)
従来の蒸気凝縮装置のベントシステムを第3図について
説明する。第3図において、炉心1を内蔵した原子炉圧
力容器2には再循環ポンプ3を有する再循環ライン4、
が設けられている。なお、再循環ライン4は図中破断さ
れた状態で示しているが、通常は破断されてない。符号
5は主蒸気配管で、この主蒸気配管5から分岐して蒸気
供給ライン7が接続されている。(Prior Art) A conventional vent system for a steam condenser will be described with reference to FIG. In FIG. 3, a reactor pressure vessel 2 containing a reactor core 1 includes a recirculation line 4 having a recirculation pump 3;
is provided. Note that although the recirculation line 4 is shown in a broken state in the figure, it is normally not broken. Reference numeral 5 denotes a main steam pipe, which branches off from the main steam pipe 5 and is connected to a steam supply line 7.
蒸気凝縮装置8は蒸気をタービンへ導く主蒸気配管5か
ら分岐し遠隔操作弁6と蒸気供給ライン7を介して接続
されている。蒸気凝縮装置8は冷却プール9内に水沈し
ている。蒸気凝縮装置8の下方に接続された復水ライン
10は、遠隔操作弁11を介し原子炉圧力容器2に接続
されている。The steam condensing device 8 branches from the main steam pipe 5 that leads steam to the turbine, and is connected to a remote control valve 6 via a steam supply line 7. The steam condenser 8 is submerged in a cooling pool 9. A condensate line 10 connected below the steam condensing device 8 is connected to the reactor pressure vessel 2 via a remote control valve 11.
(発明が解決しようとする課題)
原子炉圧力容器2と原子炉内冷却材を循環させる再循環
ポンプ3および再循環ライン4において、図示のように
再循環ライン4が破損する冷却材喪失事故が起きた場合
には主蒸気配管5は主蒸気隔能弁12によりすみやかに
しゃ断される。次に遠隔操作弁6を開くことによって原
子炉圧力容器2内の蒸気は蒸気供給ライン7を介し蒸気
凝縮装置8へと導びかれ凝縮し復水ライン10から遠隔
操作弁]1を介し原子炉圧力容器2へと戻る。さらに炉
心1を冷却する非常時冷却系が作動するとともに原子炉
圧力容器2内が一時的に負圧となり、原子炉圧力容器2
の周辺に充満している窒素が破損部から原子炉圧力容器
2へと流入し蒸気凝縮装置8まで到達すると蒸気凝縮装
置8での凝縮能力が低下し、除熱の能力は所定の性能を
期待できなくなる。(Problems to be Solved by the Invention) In the reactor pressure vessel 2 and the recirculation pump 3 and recirculation line 4 that circulate the coolant in the reactor, a coolant loss accident in which the recirculation line 4 is damaged as shown in the figure occurs. If this occurs, the main steam pipe 5 is immediately shut off by the main steam valve 12. Next, by opening the remote control valve 6, the steam in the reactor pressure vessel 2 is guided to the steam condensing device 8 via the steam supply line 7, where it is condensed. Return to pressure vessel 2. Furthermore, the emergency cooling system that cools the reactor core 1 is activated, and the inside of the reactor pressure vessel 2 temporarily becomes negative pressure.
When the nitrogen filling the area around the reactor flows into the reactor pressure vessel 2 from the damaged part and reaches the steam condensing device 8, the condensing capacity of the steam condensing device 8 decreases, and the heat removal capacity reaches the specified performance. become unable.
本発明は上記課題を解決するためになされたもので、原
子炉の冷却材喪失事故時において、蒸気をタービンへと
導く主蒸気配管が隔離された場合、主蒸気配管より分岐
した配管に取り付けられた蒸気凝縮装置により蒸気は凝
縮される。また蒸気凝縮装置に窒素が混入した場合にジ
ェットスクラバーを用いて窒素を除去することにより蒸
気凝縮装置の凝縮能力を維持し、冷却材喪失事故後に確
実に作動を続ける蒸気凝縮装置のベントシステムを提供
することにある。The present invention has been made to solve the above-mentioned problems, and when the main steam piping leading steam to the turbine is isolated in the event of a loss of coolant accident in a nuclear reactor, the present invention can be installed on a piping branched from the main steam piping. The steam is condensed by a steam condenser. In addition, we provide a vent system for steam condensers that maintains the condensing capacity of steam condensers by removing nitrogen using a jet scrubber when nitrogen gets mixed into the steam condensers, and ensures continued operation after a loss of coolant accident. It's about doing.
(課題を解決するための手段)
本発明は一方の基端を原子炉主蒸気配管に他方の基端を
原子炉復水ラインに接続し冷却プールに水沈した蒸気凝
縮装置と、この蒸気凝縮装置の復水ラインにジエンl−
スクラバーを設け、このジエン1〜スクラバーと前記蒸
気凝縮装置の気相部との間に遠隔操作弁を介して窒素ペ
ン1〜ラインを接続し、さらに前記ジェットスクラバー
の下方にヘッダータンクを設け、このヘッダータンクの
下方を前記復水ラインに接続してなることを特徴とする
。(Means for Solving the Problems) The present invention provides a steam condensing device submerged in a cooling pool with one base end connected to a reactor main steam pipe and the other base end connected to a reactor condensate line, and a steam condensing device submerged in a cooling pool. diene l- in the condensate line of the equipment.
A scrubber is provided, a nitrogen pen 1 line is connected via a remote control valve between the diene 1 scrubber and the gas phase of the steam condensing device, and a header tank is provided below the jet scrubber. It is characterized in that the lower part of the header tank is connected to the condensate line.
(作 用)
たとえば冷却材喪失事故時には主蒸気管の隔離弁が閉じ
、遠隔操作弁が開き、原子炉圧力容器内の蒸気は蒸気供
給ラインから蒸気凝縮装置に流入する。この蒸気凝縮装
置で凝縮された水は復水ラインを通して原子炉圧力容器
に戻るが、蒸気凝縮装置に窒素が混入した場合、窒素ベ
ントラインを通しジェットスクラバーによって窒素を除
去することができる。(Function) For example, in the event of a loss of coolant accident, the isolation valve in the main steam pipe closes, the remote control valve opens, and the steam in the reactor pressure vessel flows into the steam condensing device from the steam supply line. Water condensed in this steam condenser returns to the reactor pressure vessel through a condensate line, but if nitrogen gets mixed into the steam condenser, it can be removed by a jet scrubber through a nitrogen vent line.
(実施例) 本発明に係る第1の実施例を第1図によって説明する。(Example) A first embodiment according to the present invention will be described with reference to FIG.
なお、第3図と同一部分には同一符号で示し重複する部
分の説明を省略する。蒸気をタービンへ導く主蒸気配管
5より分岐して第1の遠隔操作弁6と蒸気供給ライン7
を介し蒸気凝縮装置8に接続される。蒸気凝縮装置8は
冷却プール9の中に水沈している。蒸気凝縮装置8の下
方から復水ライン】0は第2の遠隔操作弁11を介し原
子炉圧力容器2へと接続される。もう一方は第3の遠隔
操作弁13を介しジェットスクラバー16に接続される
。ジェットスクラバー16には蒸気凝縮装置8の下部側
面(気相部)から第4の遠隔操作弁14と窒素ベン1へ
ライン]5が接続されている。前記ジエン1〜スクラバ
ー14の下にはヘッダータンク17が設けられ、ヘッダ
ータンク17から復水ライン18を介し原子炉圧力容器
2に接続される。Note that the same parts as in FIG. 3 are designated by the same reference numerals, and the explanation of the overlapping parts will be omitted. A first remote control valve 6 and a steam supply line 7 branch from the main steam pipe 5 that leads steam to the turbine.
It is connected to the steam condensing device 8 via. The steam condenser 8 is submerged in a cooling pool 9. A condensate line [0] from below the steam condensing device 8 is connected to the reactor pressure vessel 2 via a second remote control valve 11. The other end is connected to a jet scrubber 16 via a third remote control valve 13. A line] 5 is connected to the jet scrubber 16 from the lower side (gas phase part) of the steam condensing device 8 to the fourth remote control valve 14 and the nitrogen vent 1. A header tank 17 is provided below the diene 1 to the scrubber 14, and the header tank 17 is connected to the reactor pressure vessel 2 via a condensate line 18.
ジエン1〜スクラバー16は加圧された水または適切な
水溶液をノズルから噴射して排ガスを吸引するとともに
液中に溶解させて清浄化したガスのみを大気中に放出す
る型式で、排ガスの吸引、浄化に使用されているものと
作用はほぼ同じものである。Diene 1 to scrubber 16 are of the type that inject pressurized water or an appropriate aqueous solution from a nozzle to suck in the exhaust gas, and discharge only the purified gas by dissolving it in the liquid into the atmosphere. The action is almost the same as that used for purification.
上記ベントシステムにおいて、冷却材喪失事故時には主
蒸気配管5を主蒸気隔離弁12によりすみやかにしゃ断
する。次に第1の遠隔操作弁6を開くことにより原子炉
圧力容器2内の蒸気は蒸気供給ライン7を介し蒸気凝縮
装置8へと導びかれ凝縮し、復水ライン10を通り第2
の遠隔操作弁」1を介し原子炉圧力容器2へと戻る。非
常用炉心冷却系が作動した後、−時的に炉圧が負圧とな
り、蒸気凝縮装置8に窒素が混入すると凝縮能力が低下
する。In the above vent system, the main steam piping 5 is promptly shut off by the main steam isolation valve 12 in the event of a loss of coolant accident. Next, by opening the first remote control valve 6, the steam in the reactor pressure vessel 2 is guided to the steam condensing device 8 via the steam supply line 7, where it is condensed, and passed through the condensate line 10 to the second
It returns to the reactor pressure vessel 2 via the remote control valve 1. After the emergency core cooling system is activated, the reactor pressure temporarily becomes negative, and if nitrogen enters the steam condensing device 8, the condensing capacity decreases.
この場合、第2の遠隔操作弁11を閉じ第3の遠隔操作
弁13、第4の遠隔操作弁14を開くことによって蒸気
凝縮装M8からの復水がジェットスクラバー16に供給
され窒素ベントライン15から流入する窒素を巻き込み
ヘッダータンク17に放出され、水はへラダータンク1
7に溜まり窒素は周辺に放たれる。ヘッダータンク17
の水は復水ラインを介し原子炉圧力容器2に戻る。この
ようにして蒸気凝縮装置8に混入した窒素をベントする
ことが出来る。In this case, by closing the second remote control valve 11 and opening the third remote control valve 13 and fourth remote control valve 14, condensate from the steam condenser M8 is supplied to the jet scrubber 16 and the nitrogen vent line 15 is supplied to the jet scrubber 16. It entrains the nitrogen flowing in from the header tank 17 and releases the water to the header tank 17.
7 and the nitrogen is released into the surrounding area. header tank 17
The water returns to the reactor pressure vessel 2 via the condensate line. In this way, nitrogen mixed into the steam condenser 8 can be vented.
本発明に係る第2の実施例を第2図によって説明する。A second embodiment according to the present invention will be explained with reference to FIG.
前記実施例との相違はジェットスクラバー14から放出
された窒素をチャンバー19で回収しサプレッションプ
ール20を送り込むようにしたものである。その他の部
分は第1の実施例と同様なので重複する部分の説明を省
略する。The difference from the previous embodiment is that nitrogen released from the jet scrubber 14 is collected in a chamber 19 and sent to a suppression pool 20. The other parts are the same as those in the first embodiment, so the explanation of the overlapping parts will be omitted.
本発明によれば、蒸気凝縮装置に流入した窒素をスムー
ズに抜き取ることが出来、蒸気凝縮装置での除熱による
蒸気凝縮が安定して行えることにより、冷却材喪失事故
後の迅速かつスムーズに作動させることができる。According to the present invention, the nitrogen that has flowed into the steam condensing device can be smoothly removed, and the steam condensing device can stably condense steam by removing heat, so that it can operate quickly and smoothly after a loss of coolant accident. can be done.
第1図は本発明に係る蒸気凝縮装置のベントシステムの
第1の実施例を示す系統図、第2図は本発明の第2の実
施例を示す蒸気調装置のベントシステムを示す系統図、
第3図は従来の蒸気凝縮装置のシステムを示す系統図で
ある。FIG. 1 is a system diagram showing a first embodiment of a vent system for a steam condensing device according to the present invention, and FIG. 2 is a system diagram showing a vent system for a steam conditioning device according to a second embodiment of the present invention.
FIG. 3 is a system diagram showing a conventional steam condensing device system.
Claims (1)
子炉復水ラインに接続し冷却プールに水沈した蒸気凝縮
装置と、この蒸気凝縮装置の復水ラインにジェットスク
ラバーを設け、このジェットスクラバーと前記蒸気凝縮
装置の気相部との間に遠隔操作弁を介して窒素ベントラ
インを接続し、さらに前記ジェットスクラバーの下方に
ヘッダータンクを設け、このヘッダータンクの下方を前
記復水ラインに接続してなることを特徴とする蒸気凝縮
装置のベントシステム。(1) A steam condensing device submerged in a cooling pool with one base end connected to the reactor main steam pipe and the other base end connected to the reactor condensate line, and a jet scrubber attached to the condensate line of this steam condensing device. A nitrogen vent line is connected between the jet scrubber and the gas phase of the steam condensing device via a remote control valve, and a header tank is provided below the jet scrubber, and a header tank is provided below the header tank. A vent system for a steam condenser that is connected to a condensate line.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1073927A JPH02253193A (en) | 1989-03-28 | 1989-03-28 | Vent system for steam condenser |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1073927A JPH02253193A (en) | 1989-03-28 | 1989-03-28 | Vent system for steam condenser |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH02253193A true JPH02253193A (en) | 1990-10-11 |
Family
ID=13532262
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1073927A Pending JPH02253193A (en) | 1989-03-28 | 1989-03-28 | Vent system for steam condenser |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH02253193A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1995010836A1 (en) * | 1993-10-12 | 1995-04-20 | Arnold Otto Winfried Reinsch | Passive decay heat removal and internal depressurization system for nuclear reactors |
| JP2014513280A (en) * | 2011-03-23 | 2014-05-29 | バブコック・アンド・ウィルコックス・ニュークリアー・エナジー・インコーポレイテッド | Energy core cooling system for pressurized water reactors |
-
1989
- 1989-03-28 JP JP1073927A patent/JPH02253193A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1995010836A1 (en) * | 1993-10-12 | 1995-04-20 | Arnold Otto Winfried Reinsch | Passive decay heat removal and internal depressurization system for nuclear reactors |
| JP2014513280A (en) * | 2011-03-23 | 2014-05-29 | バブコック・アンド・ウィルコックス・ニュークリアー・エナジー・インコーポレイテッド | Energy core cooling system for pressurized water reactors |
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