JP2577352B2 - Reactor residual heat removal equipment - Google Patents

Reactor residual heat removal equipment

Info

Publication number
JP2577352B2
JP2577352B2 JP61073482A JP7348286A JP2577352B2 JP 2577352 B2 JP2577352 B2 JP 2577352B2 JP 61073482 A JP61073482 A JP 61073482A JP 7348286 A JP7348286 A JP 7348286A JP 2577352 B2 JP2577352 B2 JP 2577352B2
Authority
JP
Japan
Prior art keywords
valve
heat exchanger
reactor
injection
downstream
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
JP61073482A
Other languages
Japanese (ja)
Other versions
JPS62229095A (en
Inventor
隆久 近藤
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
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP61073482A priority Critical patent/JP2577352B2/en
Publication of JPS62229095A publication Critical patent/JPS62229095A/en
Application granted granted Critical
Publication of JP2577352B2 publication Critical patent/JP2577352B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Cleaning In General (AREA)

Description

【発明の詳細な説明】 (産業上の利用分野) 本発明は、原子炉の残留熱除去装置に係り、特に原子
炉の停止時に原子炉を冷却するための原子炉の残留熱除
去装置に関する。
Description: TECHNICAL FIELD The present invention relates to a residual heat removing apparatus for a nuclear reactor, and more particularly to a residual heat removing apparatus for a nuclear reactor for cooling a nuclear reactor when the reactor is stopped.

(従来の技術) 一般に、沸騰水型原子力発電所においては、原子炉を
停止させた場合に、タービン系の復水器で原子炉蒸気を
凝縮させることにより原子炉冷却が行なわれるもので、
炉蒸気の発生量が少なくなると残留熱除去装置により原
子炉の冷却を行なうようにしている。
(Prior Art) Generally, in a boiling water nuclear power plant, when the reactor is shut down, the reactor steam is condensed by a turbine condenser to cool the reactor.
When the amount of generated reactor steam decreases, the reactor is cooled by the residual heat removing device.

第2図は従来の残留熱除去装置を示したもので、原子
炉圧力容器1と循環ポンプ2との間には、炉水の吸込配
管2および戻り配管4がそれぞれ接続され、上記炉水を
吸込配管3により導出し循環ポンプ2で昇圧した後、戻
り配管4を介して原子炉圧力容器1内に戻すようにして
いる。
FIG. 2 shows a conventional residual heat removing apparatus. A reactor water suction pipe 2 and a return pipe 4 are connected between a reactor pressure vessel 1 and a circulation pump 2, respectively. After being drawn out by the suction pipe 3 and pressurized by the circulation pump 2, the pressure is returned to the reactor pressure vessel 1 through the return pipe 4.

また、上記吸込配管3は、その中途部において分岐さ
れ、この分岐側配管は、途中、隔離分5,5、冷却ポンプ
6、熱交換器入口弁7、冷却水系8により冷却水を供給
される熱交換器9、熱交換器出口弁10、注入弁11および
注入逆止弁12をそれぞれ介して、上記戻り配管4の中途
部に接続されている。上記冷却ポンプ6の下流側には、
上記熱交換器9をバイパスする配管が途中熱交換器バイ
パス弁13を介して接続され、上記注入逆止弁12をバイパ
スする配管が途中、逆止弁バイパス弁14を介して設けら
れている。
Further, the suction pipe 3 is branched at an intermediate portion thereof, and the branch side pipe is supplied with cooling water by way of an isolated part 5, 5, a cooling pump 6, a heat exchanger inlet valve 7, and a cooling water system 8 on the way. The heat exchanger 9, the heat exchanger outlet valve 10, the injection valve 11, and the injection check valve 12 are connected to an intermediate portion of the return pipe 4 via each of them. On the downstream side of the cooling pump 6,
A pipe bypassing the heat exchanger 9 is connected via a heat exchanger bypass valve 13 on the way, and a pipe bypassing the injection check valve 12 is provided on the way via a check valve bypass valve 14.

さらに、上記熱交換器9の下流側は分岐され、排出弁
15を介して圧力抑制室16へ接続され、上記注入弁11の上
流側は分岐され連絡弁17,17を介して放射性廃棄物処理
設備18に接続されている。また、復水タンク19は、復水
ポンプ20を介した後、熱交換器9の上流側および下流側
に、それぞれ上流側洗浄弁21および下流側洗浄弁22を介
して接続されており、上記原子炉圧力容器1は原子炉格
納容器23内に収納されている。
Further, the downstream side of the heat exchanger 9 is branched and a discharge valve is provided.
It is connected to a pressure suppression chamber 16 via 15, and the upstream side of the injection valve 11 is branched and connected to a radioactive waste treatment facility 18 via communication valves 17, 17. Further, the condensate tank 19 is connected to the upstream side and the downstream side of the heat exchanger 9 via an upstream side cleaning valve 21 and a downstream side cleaning valve 22 after passing through a condensate pump 20, respectively. The reactor pressure vessel 1 is housed in a reactor containment vessel 23.

上記装置においては、原子炉圧力容器1内の炉水を循
環ポンプ2により常に循環させており、原子炉の停止時
には、隔離弁5側へ炉水を送り、冷却ポンプ6にて昇圧
した後、熱交換器9で冷却する。その後、冷却された炉
水は、注入弁11、注入逆止弁12および戻り配管4を通っ
て原子炉圧力容器1へ戻され、原子炉を冷却するように
している。
In the above device, the reactor water in the reactor pressure vessel 1 is constantly circulated by the circulation pump 2. When the reactor is stopped, the reactor water is sent to the isolation valve 5 side, and after the reactor pump is pressurized by the cooling pump 6, Cool in heat exchanger 9. Thereafter, the cooled reactor water is returned to the reactor pressure vessel 1 through the injection valve 11, the injection check valve 12, and the return pipe 4, so as to cool the reactor.

このような残留熱除去装置は、プラントの通常運転時
には使用されていないため、配管内の水は低温(約30
℃)で、しかも、腐食による生成物が混入している。そ
のため、すぐに運転を開始すると、原子炉の炉水温度が
約150℃と高いため熱的ショックが生じ材料の健全性上
好ましくなく、また、腐食生成物が原子炉に侵入すると
炉水中の放射性物質量が増大してしまう。
Since such a residual heat removal device is not used during normal operation of the plant, the water in the pipes has a low temperature (about 30
° C) and the product of corrosion is mixed. Therefore, if the operation is started immediately, the reactor water temperature of the reactor is as high as about 150 ° C, causing thermal shock, which is not desirable in terms of the soundness of the material. The amount of substance increases.

そこで系統の運転前に従来から配管の洗浄および暖機
を行なうようにしている。
Therefore, prior to the operation of the system, cleaning and warming of the pipes have been conventionally performed.

まず、系統の洗浄を行なう場合は、隔離弁5および注
入弁11を閉じ、連絡弁17および下流側洗浄弁22を開け
る。すると、復水タンク19から復水ポンプ20を経て昇圧
された復水は、注入弁11の上流側を洗浄して放射性廃棄
物処理設備18へ送られる。次に、下流側洗浄弁22および
熱交換器バイパス弁13を閉じ、上流側洗浄弁21、熱交換
器入口弁7および出口弁10を開くことにより、冷却ポン
プ6、熱交換器9が洗浄され、その後、復水は放射性廃
棄物処理設備18へ送られる。最後に、熱交換器入口弁7
および出口弁10を閉じ、バイパス弁13を開き、このバイ
パス弁13の前後の配管を洗浄する。
First, when cleaning the system, the isolation valve 5 and the injection valve 11 are closed, and the communication valve 17 and the downstream side cleaning valve 22 are opened. Then, the condensed water pressurized from the condensate tank 19 via the condensate pump 20 is washed on the upstream side of the injection valve 11 and sent to the radioactive waste treatment equipment 18. Next, the cooling pump 6 and the heat exchanger 9 are cleaned by closing the downstream side cleaning valve 22 and the heat exchanger bypass valve 13 and opening the upstream side cleaning valve 21, the heat exchanger inlet valve 7 and the outlet valve 10. Thereafter, the condensate is sent to the radioactive waste treatment facility 18. Finally, the heat exchanger inlet valve 7
The outlet valve 10 is closed, the bypass valve 13 is opened, and the piping before and after the bypass valve 13 is washed.

続いて、暖機を行なう場合は、各洗浄弁21,22および
連絡弁17を閉じ、注入逆止弁12の前後の圧力が均圧状態
であれば逆止弁バイパス弁14を開くことができるので、
注入弁11、逆止弁バイパス弁14、注入逆止弁12の順に開
く。さらに、熱交換器出口弁10を閉じ、熱交換器入口弁
7およびバイパス弁13を開く。この状態で排出弁15を徐
々に開きその開度を調節すれば、高温の炉水は注入逆止
弁12を通って配管および熱交換器9を暖めた後、圧力抑
制室16に流入する。次に、注入弁11、注入逆止弁12、逆
止弁バイパス弁14、熱交換器入口弁7を閉じ、隔離弁
5、熱交換器バイパス弁13および出口弁10を開く。そし
て、排出弁15を徐々に開くことにより、冷却ポンプ6
等、熱交換器9の上流側の暖機が行なわれる。
Subsequently, when performing warm-up, the cleaning valves 21 and 22 and the communication valve 17 are closed, and the check valve bypass valve 14 can be opened if the pressure before and after the injection check valve 12 is equalized. So
The injection valve 11, the check valve bypass valve 14, and the injection check valve 12 are opened in this order. Further, the heat exchanger outlet valve 10 is closed, and the heat exchanger inlet valve 7 and the bypass valve 13 are opened. If the discharge valve 15 is gradually opened and its opening is adjusted in this state, the high-temperature reactor water flows into the pressure suppression chamber 16 after warming the pipe and the heat exchanger 9 through the injection check valve 12. Next, the injection valve 11, the injection check valve 12, the check valve bypass valve 14, and the heat exchanger inlet valve 7 are closed, and the isolation valve 5, the heat exchanger bypass valve 13, and the outlet valve 10 are opened. By gradually opening the discharge valve 15, the cooling pump 6
For example, the upstream side of the heat exchanger 9 is warmed up.

(発明が解決しようとする課題) 上述のように、残留熱除去装置の暖機を行なった場合
には、炉水が圧力抑制室16に流入するようになっている
が、圧力抑制室16内の水は、規定水位を越えた場合に室
外へ放出されるため、炉水により持ち込まれた放射性物
質が無計画に管理されることになり、発電所内の放射能
汚染防止上好ましくない。
(Problems to be Solved by the Invention) As described above, when the residual heat removing device is warmed up, the reactor water flows into the pressure suppression chamber 16. Is discharged outside the room when the water level exceeds a specified level, so that radioactive substances brought in by the reactor water are unplannedly managed, which is not preferable for preventing radioactive contamination in the power plant.

そのために、暖機時に排出される炉水を、放射性廃棄
物処理設備18に送って処理することも考えられるが、放
射性廃棄物処理設備18の最高使用温度が約70℃であるた
め、高温の炉水を直接放射性廃棄物処理設備18に送るこ
とができないという課題を有している。
For this purpose, it is conceivable that the reactor water discharged during warm-up is sent to the radioactive waste treatment facility 18 for treatment.However, since the maximum operating temperature of the radioactive waste treatment facility 18 is about 70 ° C., There is a problem that the reactor water cannot be sent directly to the radioactive waste treatment facility 18.

本発明は上記した点に鑑みてなされたもので、暖機時
に炉水を放射性廃棄物処理設備へ移送することができ、
放射性物質の計画的な処理を行なうことのできる原子炉
の残留熱除去装置を提供することを目的とするものであ
る。
The present invention has been made in view of the above points, it is possible to transfer the reactor water to the radioactive waste treatment equipment during warm-up,
It is an object of the present invention to provide an apparatus for removing residual heat of a nuclear reactor capable of performing a planned treatment of radioactive materials.

(課題を解決するための手段) 上記目的を達成すために本発明は、原子炉圧力容器と
循環ポンプの吸込口とを接続する吸込配管から冷却材を
導出し、この冷却材を熱交換器で冷却した後に前記原子
炉圧力容器と前記循環ポンプの吐出口とを接続する戻り
配管に戻すようにした循環配管系を有する原子炉の残留
熱除去装置において、前記循環配管系は、前記吸込配管
と戻り配管の接続部近傍にそれぞれ隔離弁、注入弁、注
入逆止弁およびこの注入逆止弁の上下流に接続されるバ
イパス配管に設けられた逆止弁バイパス弁を有し、前記
隔離弁の下流近傍位置と注入弁の上流近傍位置でそれぞ
れ上流側洗浄弁と下流側洗浄弁を介して復水タンクと連
通され、前記熱交換器は、その上流側と下流側にそれぞ
れ熱交換器入口弁と残留熱除去装置の暖機運転時に閉動
作される熱交換器出口弁を有し、前記熱交換器入口弁の
上流側と熱交換器出口弁の下流側の配管は、熱交換器バ
イパス弁を有する熱交換器バイパス配管によって接続さ
れ、前記熱交換器と前記熱交換器出口弁の間の配管は、
残留熱除去装置の暖機運転時に開動作される連絡弁を介
して放射性廃棄物処理設備と連通されていることを特徴
とする原子炉の残留熱除去装置を提供する。
(Means for Solving the Problems) In order to achieve the above object, the present invention derives a coolant from a suction pipe connecting a reactor pressure vessel and a suction port of a circulation pump, and transfers the coolant to a heat exchanger. In a residual heat removing device for a nuclear reactor having a circulation piping system configured to return to a return piping connecting the reactor pressure vessel and the discharge port of the circulation pump after cooling in the reactor, the circulation piping system includes the suction piping. And an isolation valve, an injection valve, an injection check valve, and a check valve provided in a bypass pipe connected upstream and downstream of the injection check valve, respectively, near the connection portion of the return pipe and the isolation valve. At the downstream vicinity position and at the upstream vicinity position of the injection valve, respectively, are communicated with the condensate tank via the upstream cleaning valve and the downstream cleaning valve, respectively, and the heat exchanger is provided with a heat exchanger inlet at its upstream side and downstream side, respectively. Warm-up of valves and residual heat removal equipment It has a heat exchanger outlet valve that is closed at the time of rotation, and a pipe upstream of the heat exchanger inlet valve and a pipe downstream of the heat exchanger outlet valve is a heat exchanger bypass pipe having a heat exchanger bypass valve. Connected, piping between the heat exchanger and the heat exchanger outlet valve,
A residual heat removal device for a nuclear reactor, characterized in that the residual heat removal device is connected to a radioactive waste treatment facility via a communication valve that is opened during a warm-up operation of the residual heat removal device.

(作 用) この様に構成された本発明は、熱交換器の下流側の暖
機を行なう場合は、注入弁、注入逆止弁、逆止弁バイパ
ス弁、熱交換器バイパス弁および熱交換器入口弁を開
き、熱交換器出口弁を閉じ、連絡弁を徐々に開いて炉水
により配管および熱交換器を暖める。このとき、炉水が
直接放射性廃棄物処理設備に送られるので、放射性物質
の計画的な処理が可能となり、しかも常時流れる冷却水
と熱交換器において熱交換されるので、炉水は充分に冷
却された後に放射性廃棄物処理設備に流入することにな
る。
(Operation) According to the present invention configured as described above, when warming up the downstream side of the heat exchanger, the injection valve, the injection check valve, the check valve bypass valve, the heat exchanger bypass valve, and the heat exchange Open the unit inlet valve, close the heat exchanger outlet valve, gradually open the communication valve, and warm the piping and heat exchanger with reactor water. At this time, since the reactor water is sent directly to the radioactive waste treatment facility, the radioactive material can be systematically treated, and the heat is exchanged with the constantly flowing cooling water in the heat exchanger. After that, it will flow into the radioactive waste treatment facility.

また、上流側の暖機を行なう場合は、熱交換器バイパ
ス弁および熱交換器出口弁を閉じたまま、注入弁、注入
逆止弁、逆止弁バイパス弁を閉じ、隔離弁を開く。そし
て、連絡弁を徐々に開いて炉水を送るものであり、この
場合も炉水が熱交換器により冷却されるため、放射性物
質の確実な処理を行なうことができる。
When warming up the upstream side, the injection valve, the injection check valve, and the check valve bypass valve are closed and the isolation valve is opened with the heat exchanger bypass valve and the heat exchanger outlet valve closed. Then, the communication valve is gradually opened to supply the reactor water. In this case, the reactor water is cooled by the heat exchanger, so that the radioactive material can be reliably treated.

(実施例) 以下、本発明の一実施例を第1図を参照して説明し、
第2図と同一部分には同一符号を付してその構成説明は
省略する。
Example An example of the present invention will be described below with reference to FIG.
The same parts as those in FIG. 2 are denoted by the same reference numerals, and the description of the configuration will be omitted.

第1図において本実施例は、従来例と比較して、暖機
で使用した炉水を排出弁を介して圧力抑制室に導かず、
連絡弁17,17および放射性廃棄物処理設備18を熱交換器
9の下流側に接続するようにし、その他の部分は、第2
図に示すものと同様である。
In FIG. 1, the present embodiment is different from the conventional example in that the reactor water used for warming-up is not guided to the pressure suppression chamber through the discharge valve.
The communication valves 17, 17 and the radioactive waste treatment equipment 18 are connected to the downstream side of the heat exchanger 9, and the other parts are connected to the second
It is similar to that shown in the figure.

本実施例において、まず、洗浄を行なう場合は、下流
側洗浄弁22、熱交換器出口弁10を開き、熱交換器バイパ
ス弁13を閉じ、連絡弁17,17を開くことにより、復水タ
ンク19の復水は熱交換器9の下流側配管を洗浄して放射
性廃棄物処理設備18へ流れ込む。次に、熱交換器出口弁
10を閉じ、熱交換器バイパス弁13および入口弁7を開く
ことにより、熱交換器9およびバイパス弁13の前後配管
が洗浄される。そして、最後に熱交換器バイパス弁13、
下流側洗浄弁22を閉じ、上流側洗浄弁21を開くことによ
り、冷却ポンプ6、熱交換器9が洗浄されるものであ
る。
In the present embodiment, first, when cleaning is performed, the downstream side cleaning valve 22, the heat exchanger outlet valve 10 is opened, the heat exchanger bypass valve 13 is closed, and the communication valves 17, 17 are opened, so that the condensate tank is opened. The condensate 19 cleans the piping downstream of the heat exchanger 9 and flows into the radioactive waste treatment facility 18. Next, the heat exchanger outlet valve
By closing 10 and opening the heat exchanger bypass valve 13 and the inlet valve 7, the pipes before and after the heat exchanger 9 and the bypass valve 13 are cleaned. And finally, the heat exchanger bypass valve 13,
By closing the downstream cleaning valve 22 and opening the upstream cleaning valve 21, the cooling pump 6 and the heat exchanger 9 are cleaned.

続いて、暖機を行なう場合は、基本的に従来のものと
同様で排出弁の代わりに連絡弁17を徐々に開くようにす
ればよい。すなわち、熱交換器9の下流側の暖機を行な
う場合は、注入弁11、逆止弁バイパス弁14、注入逆止弁
15、熱交換器バイパス弁13および熱交換器入口弁7を開
き、熱交換器出口弁10を閉じ、連絡弁17を徐々に開いて
炉水により配管および熱交換器9を暖める。このとき、
炉水が直接放射廃棄物処理設備18に送られるので、放射
性物質の計画的な処理が可能となり、しかも常時流れる
冷却水と熱交換器9において熱交換されるので、炉水は
充分に冷却された後に放射性廃棄物処理設備に流入する
ことになる。
Subsequently, when warming up, the communication valve 17 may be gradually opened instead of the discharge valve basically in the same manner as the conventional one. That is, when warming up the downstream side of the heat exchanger 9, the injection valve 11, the check valve bypass valve 14, the injection check valve
15. The heat exchanger bypass valve 13 and the heat exchanger inlet valve 7 are opened, the heat exchanger outlet valve 10 is closed, the communication valve 17 is gradually opened, and the piping and the heat exchanger 9 are heated by the reactor water. At this time,
Since the reactor water is directly sent to the radiant waste treatment facility 18, the radioactive material can be systematically treated, and the heat is exchanged with the constantly flowing cooling water in the heat exchanger 9, so that the reactor water is sufficiently cooled. After that, it will flow into the radioactive waste treatment facility.

また、上流側の暖機を行なう場合は、熱交換器バイパ
ス弁13および熱交換器出口弁10を閉じたまま、注入弁1
1、注入逆止弁12、逆止弁バイパス弁14を閉じ、隔離弁
5を開く。そして、連絡弁17を徐々に開いて炉水を送る
ものであり、この場合も炉水が熱交換器9により冷却さ
れるため、放射性物質の確実な処理を行なうことができ
る。
When warming up the upstream side, the injection valve 1 is kept closed with the heat exchanger bypass valve 13 and the heat exchanger outlet valve 10 closed.
1. Close the injection check valve 12, the check valve bypass valve 14, and open the isolation valve 5. Then, the communication valve 17 is gradually opened to feed the reactor water. In this case as well, the reactor water is cooled by the heat exchanger 9, so that the radioactive substance can be reliably treated.

なお、本実施例において、暖機時に使用された炉水は
従来も使用している熱交換器9によって充分冷却するこ
とができるので、熱交換器9の容量を本発明の実施にと
もなって増大させる必要がなく、従来使用している範囲
内で設備の拡大なしに本発明を実施することができる。
よって、原子力発電所内の限られたスペースの範囲内で
より性能の向上した原子炉の残留熱除去装置を得ること
ができる。
In this embodiment, since the reactor water used at the time of warm-up can be sufficiently cooled by the conventionally used heat exchanger 9, the capacity of the heat exchanger 9 is increased with the implementation of the present invention. Therefore, the present invention can be implemented without expanding the equipment within the range conventionally used.
Therefore, it is possible to obtain an apparatus for removing residual heat of a nuclear reactor with improved performance within a limited space in a nuclear power plant.

(発明の効果) 以上述べたように本発明に係る原子炉の残留熱除去装
置は、装置の暖機時に使用した全ての炉水を熱交換器で
冷却した後、放射性廃棄物処理設備に送ることができる
ので、放射性物質の計画的処理が可能となり、しかも、
圧力抑制室への汚染源の低減を図ることができる。さら
に、圧力制御室への配管も不要となり、さらには暖機時
に使用された炉水は残留熱除去装置の熱交換器によって
充分冷却することができ、熱交換器の容量を本発明の実
施にともなって増大させる必要がなく、設備の拡大なし
に本発明を実施することができる。
(Effect of the Invention) As described above, the reactor residual heat removal apparatus according to the present invention cools all the reactor water used when the apparatus is warmed up by the heat exchanger, and then sends it to the radioactive waste treatment facility. That allows for the planned treatment of radioactive material,
It is possible to reduce the number of contamination sources in the pressure suppression chamber. Further, piping to the pressure control chamber is not required, and the reactor water used during warm-up can be sufficiently cooled by the heat exchanger of the residual heat removing device, and the capacity of the heat exchanger is reduced in the practice of the present invention. Therefore, the present invention can be implemented without increasing the equipment.

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

第1図は本発明の一実施例に係る原子炉の残留熱除去装
置を示す系統図、第2図は原子炉の残留熱除去装置の従
来例を示す系統図である。 1……原子炉圧力容器、2……循環ポンプ、3……吸込
配管、4……戻り配管、5……隔離弁、7……熱交換器
入口弁、9……熱交換器、10……熱交換器出口弁、11…
…注入弁、12……注入逆止弁、13……熱交換器バイパス
弁、14……逆止弁バイパス弁、17……連絡弁、18……放
射性廃棄物処理設備、19……復水タンク、21……上流側
洗浄弁、22……下流側洗浄弁。
FIG. 1 is a system diagram showing a residual heat removing device for a nuclear reactor according to one embodiment of the present invention, and FIG. 2 is a system diagram showing a conventional example of a residual heat removing device for a nuclear reactor. 1 ... Reactor pressure vessel, 2 ... Circulation pump, 3 ... Suction pipe, 4 ... Return pipe, 5 ... Isolation valve, 7 ... Heat exchanger inlet valve, 9 ... Heat exchanger, 10 ... … Heat exchanger outlet valve, 11…
... injection valve, 12 ... injection check valve, 13 ... heat exchanger bypass valve, 14 ... check valve bypass valve, 17 ... communication valve, 18 ... radioactive waste treatment equipment, 19 ... condensate Tank, 21 ... upstream cleaning valve, 22 ... downstream cleaning valve.

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】原子炉圧力容器と循環ポンプの吸込口とを
接続する吸込配管から冷却材を導出し、この冷却材を熱
交換器で冷却した後に前記原子炉圧力容器と前記循環ポ
ンプの吐出口とを接続する戻り配管に戻すようにした循
環配管系を有する原子炉の残留熱除去装置において、 前記循環配管系は、前記吸込配管と戻り配管の接続部近
傍にそれぞれ隔離弁、注入弁、注入逆止弁およびこの注
入逆止弁の上下流に接続されるバイパス配管に設けられ
た逆止弁バイパス弁を有し、前記隔離弁の下流近傍位置
と注入弁の上流近傍位置でそれぞれ上流側洗浄弁と下流
側洗浄弁を介して復水タンクと連通され、 前記熱交換器は、その上流側と下流側にそれぞれ熱交換
器入口弁と残留熱除去装置の暖機運転時に閉動作される
熱交換器出口弁を有し、 前記熱交換器入口弁の上流側と熱交換器出口弁の下流側
の配管は、熱交換器バイパス弁を有する熱交換器バイパ
ス配管によって接続され、 前記熱交換器と前記熱交換器出口弁の間の配管は、残留
熱除去装置の暖機運転時に開動作される連絡弁を介して
放射性廃棄物処理設備と連通されていることを特徴とす
る原子炉の残留熱除去装置。
1. A coolant is drawn out from a suction pipe connecting a reactor pressure vessel and a suction port of a circulation pump, and the coolant is cooled by a heat exchanger, and then discharged from the reactor pressure vessel and the circulation pump. In a residual heat removing device for a nuclear reactor having a circulation piping system configured to return to a return piping connecting an outlet, the circulation piping system includes an isolation valve, an injection valve, and a valve near a connection between the suction piping and the return piping, respectively. An injection check valve and a check valve provided on a bypass pipe connected to the upstream and downstream of the injection check valve, wherein the check valve is located upstream and downstream of the isolation valve and upstream of the injection valve, respectively. The heat exchanger is communicated with a condensate tank via a washing valve and a downstream washing valve, and the heat exchanger is closed on the upstream side and the downstream side during a warm-up operation of the heat exchanger inlet valve and the residual heat removing device, respectively. A heat exchanger outlet valve, wherein the heat The pipes upstream of the exchanger inlet valve and downstream of the heat exchanger outlet valve are connected by a heat exchanger bypass pipe having a heat exchanger bypass valve, between the heat exchanger and the heat exchanger outlet valve. The residual heat removal device for a nuclear reactor, wherein the pipe is connected to the radioactive waste treatment facility via a communication valve that is opened when the residual heat removal device is warmed up.
JP61073482A 1986-03-31 1986-03-31 Reactor residual heat removal equipment Expired - Lifetime JP2577352B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61073482A JP2577352B2 (en) 1986-03-31 1986-03-31 Reactor residual heat removal equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61073482A JP2577352B2 (en) 1986-03-31 1986-03-31 Reactor residual heat removal equipment

Publications (2)

Publication Number Publication Date
JPS62229095A JPS62229095A (en) 1987-10-07
JP2577352B2 true JP2577352B2 (en) 1997-01-29

Family

ID=13519540

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61073482A Expired - Lifetime JP2577352B2 (en) 1986-03-31 1986-03-31 Reactor residual heat removal equipment

Country Status (1)

Country Link
JP (1) JP2577352B2 (en)

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5293900A (en) * 1976-02-02 1977-08-06 Hitachi Ltd Purififying method and device for nuclear reactor
JPS5941155A (en) * 1982-09-01 1984-03-07 Hitachi Ltd Current collecting ring protecting device for generator of vehicle

Also Published As

Publication number Publication date
JPS62229095A (en) 1987-10-07

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