JPS62129791A - Decay-heat removing operating method - Google Patents
Decay-heat removing operating methodInfo
- Publication number
- JPS62129791A JPS62129791A JP60269594A JP26959485A JPS62129791A JP S62129791 A JPS62129791 A JP S62129791A JP 60269594 A JP60269594 A JP 60269594A JP 26959485 A JP26959485 A JP 26959485A JP S62129791 A JPS62129791 A JP S62129791A
- Authority
- JP
- Japan
- Prior art keywords
- steam
- steam generator
- water
- temperature
- liquid sodium
- 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
- Investigation Of Foundation Soil And Reinforcement Of Foundation Soil By Compacting Or Drainage (AREA)
- Separation Of Gases By Adsorption (AREA)
- Water Treatment By Sorption (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】
[発明の技i・1:i分野]
本発明は、高速増殖炉の崩壊熱の除去を行なう崩壊熱除
去運転方法に関する。Detailed Description of the Invention [Technique of the Invention i.1: Field of the Invention] The present invention relates to a decay heat removal operation method for removing decay heat of a fast breeder reactor.
[発明の技術的背景とその問題点コ
核分裂性物質を燃焼させ、エネルギーを取り出すととも
に、燃料親物質から有用な核分裂性物質を増殖する高速
増殖炉は、有効な原子炉として現在その研究開発が進め
られている。[Technical background of the invention and its problems] The fast breeder reactor, which burns fissile material to extract energy and breed useful fissile material from the parent fuel material, is currently undergoing research and development as an effective nuclear reactor. It is progressing.
第3図はこのような高速増殖炉プラントの一例の要部を
示すもので、図において符号1は蒸気発生器を示してい
る。この蒸気発生器1の高温側に゛ は、液体ナトリウ
ムを流通するための液体ナトリウム入口配管2と、液体
ナトリウム出口配管3が接続されており、低温側には、
蒸気発生器1で発生した蒸気をタービン(図示せず)へ
送るための主蒸気配管4と、復水器(図示せず)から脱
気器5、給水ポンプ6、給水加熱器7を経由して蒸気発
生器1に給水する給水配管8が接続されている。FIG. 3 shows the main parts of an example of such a fast breeder reactor plant, and in the figure, reference numeral 1 indicates a steam generator. A liquid sodium inlet pipe 2 and a liquid sodium outlet pipe 3 for flowing liquid sodium are connected to the high temperature side of the steam generator 1, and to the low temperature side,
The steam generated in the steam generator 1 is sent to a turbine (not shown) through a main steam pipe 4, and from a condenser (not shown) via a deaerator 5, a feed water pump 6, and a feed water heater 7. A water supply pipe 8 that supplies water to the steam generator 1 is connected thereto.
なお給水配管8には、給水流量を調節するための給水調
節弁9が介挿されている。Note that a water supply adjustment valve 9 for adjusting the water supply flow rate is inserted into the water supply pipe 8.
また蒸気発生器1の周囲には、高速増殖炉の起動、停止
時のみに使用される再循環システムが付加されており、
この再循環システムは主蒸気配管4から気水分離器10
に蒸気を導入するための導入配管11、気水分離器10
で分離された蒸気を主熱気配管4に戻ず蒸気配管12、
分離された水を蒸気発生器1に再循環するための再循環
配管13、および再循環ポンプ14と、これらの流路を
切り替えるために各配管に介挿された弁15.16.1
7および逆止弁18.19により構成されている。Additionally, a recirculation system is added around the steam generator 1, which is used only when starting and stopping the fast breeder reactor.
This recirculation system runs from the main steam pipe 4 to the steam separator 10.
Introductory piping 11 for introducing steam into the water separator 10
steam pipe 12 without returning the steam separated to the main hot air pipe 4;
Recirculation piping 13 and recirculation pump 14 for recirculating the separated water to the steam generator 1 and valves 15.16.1 inserted in each piping to switch these flow paths.
7 and check valves 18 and 19.
上記構成の高速増TJli′1炉プラントでは、炉心で
発生した熱エネルギーを、液体ナトリウムを循環させる
ことにより取出し、蒸気発生器1で給水配管8から給水
される水を蒸気化し、主蒸気配管4によってタービンへ
導き、タービンを回転させる。In the high speed increase TJli'1 reactor plant with the above configuration, the thermal energy generated in the reactor core is extracted by circulating liquid sodium, the water supplied from the water supply pipe 8 is vaporized in the steam generator 1, and the water supplied from the main steam pipe 8 is to the turbine, which rotates the turbine.
なお給水加熱器7の高温側には、蒸気の一部が導入され
、給水の加熱が行なわれる。A portion of the steam is introduced into the high temperature side of the feed water heater 7 to heat the feed water.
このような高速増殖炉プランI・で炉心が停止された場
合には、崩壊熱の除去を行なう必要があるので、給水ポ
ンプ6の運転が続けられ、蒸気発生器1へ給水が続(プ
られる。しかしなからこのようにして崩壊熱の除去を行
なうと、タービントリップに伴う給水7111λ(1蒸
気源の喪失により、給水1〕n熱器7の出口給水温度は
脱気器5の飽和温度まで低下する。これに伴って蒸気発
生器1の出ロ液体犬トリウム温度も低下することになる
。この温度低下幅か人き1ぎると、蒸気発生器1の出口
液体ナトリウムノズル部に大きな熱衝撃が加わり、プラ
ントの鮭仝性および安全性が損われる危険1生が必ると
いう問題が必る。When the reactor core is shut down in such a fast breeder reactor plan I, it is necessary to remove decay heat, so the feed water pump 6 continues to operate, and the water supply to the steam generator 1 is continued. However, when the decay heat is removed in this way, the temperature of the feed water at the outlet of the heater 7 decreases to the saturation temperature of the deaerator 5. Along with this, the temperature of the liquid sodium thorium at the outlet of the steam generator 1 also decreases.If this temperature decreases too much, a large thermal shock will occur at the outlet liquid sodium nozzle of the steam generator 1. In addition, there is a risk that the salmon quality and safety of the plant will be compromised.
[発明の目的]
本発明はかかる問題に対処してなされたもので、蒸気発
生器出口液体ナトリウムノズル部に加わる熱衝撃を緩和
して、高速増殖炉プラン1〜の健仝1生および安全性が
損われることを防止することのできる崩壊熱除去運転方
法を提供しようとするものである。[Objective of the Invention] The present invention has been made in response to such problems, and improves the health and safety of fast breeder reactor plans 1 to 1 by mitigating the thermal shock applied to the liquid sodium nozzle at the outlet of the steam generator. The purpose of the present invention is to provide a decay heat removal operation method that can prevent damage to the decay heat.
[発明の概要]
すなわら本発明は、蒸気発生器の低温側に給水し、この
蒸気発生器の高温側に循環された液体す1〜1ノウムを
冷却して崩壊熱の除去を行なう崩壊熱除去運転方法にお
いて、前記蒸気発生器に復水器から給水するとともに、
前記蒸気発生器内で発生づる蒸気を再循環シスデム内の
気水分離器に導入し、この気水分離器により分離された
水を前記蒸気発生器に再循環し、かつ、首記蒸気発生器
の液体ナトリウム出口測温度および温度変化率を監視し
、この液体ナトリウム出口測温度および温度変化率がそ
れぞれあらかじめ設定された設定1直を越えた場合には
、それぞれのδ2定1直からの1lii+’を差に応じ
て前記復水器からの給水流辺を減少ざUることにより、
蒸気発生器出口液体ナトリウムノズル部に加わる熱衝撃
を緩和して、高速増殖炉プラントの叶全11あJ、び安
全性が損われることを防止することのできるようにした
ものである。[Summary of the Invention] In other words, the present invention provides a decay system in which water is supplied to the low-temperature side of a steam generator, and the liquid 1 to 1 noum circulated to the high-temperature side of the steam generator is cooled to remove decay heat. In the heat removal operation method, water is supplied to the steam generator from a condenser, and
The steam generated in the steam generator is introduced into a steam-water separator in a recirculation system, and the water separated by the steam-water separator is recycled to the steam generator, and Monitor the liquid sodium outlet temperature and temperature change rate, and if the liquid sodium outlet temperature and temperature change rate exceed the preset 1st shift, 1lii+' from each δ2 constant 1st shift. By reducing the water supply stream from the condenser according to the difference,
The thermal shock applied to the liquid sodium nozzle at the exit of the steam generator can be alleviated to prevent damage to the safety and performance of the fast breeder reactor plant.
[発明の実施例]
以下、本発明方法の詳細を一実施例について図面を用い
て説明する。[Embodiment of the Invention] Hereinafter, details of the method of the present invention will be explained with reference to the drawings for one embodiment.
第1図dプよび第2図は、本発明の一実施例の方法に用
いる制御装置および制御装置を配置された高速増殖炉プ
ラントの構成を示している。なお第3図に示す高速増殖
炉プラントと同一部分には、同一符号を付して重複した
説明は省略りる。FIGS. 1d and 2 show the configuration of a fast breeder reactor plant in which a control device and a control device used in the method of one embodiment of the present invention are arranged. Note that the same parts as those in the fast breeder reactor plant shown in FIG. 3 are given the same reference numerals and redundant explanations will be omitted.
第1図および第2図において符5Q20は、制御装置を
示している。この制御装置20は蒸気発生器1の入口液
体ナトリウム温度を入力され、給水流?目標値を出力す
る関数発生器21と、蒸気発生器1の出口液体す1〜す
【クム温度を入ツノされ、あらかじめ設定された温度設
定置と比較し、蒸気発生器1の出口液体ナトリウム温度
がこの温度32定直以下に低下した場合には、その[偏
差に応じて給水流量目標値を減少修正づ−る温度監視装
置22と、蒸気発生器1の出口液体ナトリウム温度を入
力され、温度変化率を出力する微分器23と、この微分
器23からの出力を入力され、この温度変化率とあらか
じめ設定された温度変化率設定値とを比較し、この温度
変化率か温度変化率設定値を越えた場合には、給水流m
目標値を減少修正する温度変化率監視装置24と、給水
流量目標値と給水流量を入力され、その1偏差に応じて
給水調節弁を制御する給水調節弁制御装置25とから構
成されている。In FIGS. 1 and 2, reference numeral 5Q20 indicates a control device. This control device 20 is inputted with the inlet liquid sodium temperature of the steam generator 1 and determines the feed water flow rate. A function generator 21 outputs a target value, and a temperature of the outlet liquid sodium of the steam generator 1 is compared with a preset temperature setting point. If the temperature drops below this temperature 32, the temperature monitoring device 22 decreases and corrects the feed water flow rate target value according to the deviation. A differentiator 23 outputs the rate of change, and the output from this differentiator 23 is input, and this temperature change rate is compared with a preset temperature change rate setting value to determine whether this temperature change rate or the temperature change rate set value If the water flow exceeds m
It is comprised of a temperature change rate monitoring device 24 that corrects the target value by decreasing it, and a feed water regulating valve control device 25 that receives the feed water flow rate target value and the feed water flow rate and controls the feed water regulating valve according to one deviation thereof.
この実施例の方法では、崩壊熱の除去を行う場合、まず
流路1.7I換用の弁158閉とし、弁1Gを間として
、蒸気発生器1内で発生した蒸気を気水分離器10に導
くとと乙に、制御装置20を作動ざlる。In the method of this embodiment, when the decay heat is removed, first the valve 158 for exchange of the flow path 1.7I is closed, and the steam generated in the steam generator 1 is transferred to the steam separator 10 with the valve 1G in between. The control device 20 is activated when the controller 20 is guided.
制■1装置20ては、蒸気発生器1の入口液体す1−リ
ウム温度によって給水流量目漂舶を決定するとともに、
蒸気発生器1の出ロ液体J団ノウム温度および温度変化
率を監視し、このどららか一方必るいは両方かあらかじ
め設定された設定値を越えた場合には、給水流量目標値
を減少;4正して、給水温度が急激に低下した場合には
、給水流量を5問節することにより蒸気発生器1の出[
」)1タ体ツートリウムノズル部に熱衝撃か11uねる
ことを防止する。The control device 20 determines the water supply flow rate depending on the temperature of the liquid at the inlet of the steam generator 1, and
Monitor the output liquid temperature and temperature change rate of the steam generator 1, and if one or both of these exceed a preset set value, reduce the feed water flow rate target value; 4 Correctly, if the feed water temperature drops suddenly, the output of the steam generator 1 can be reduced by adjusting the feed water flow rate.
'') Prevents thermal shock from bending to the 1-piece tsutorium nozzle part.
そして、蒸気駆動式の給水ポンプ6は、蒸気の減少にと
もなって運転が困難になるので、気水分離器10に分離
された水が蓄えられ、水位かある程度上昇づ−ると、弁
17を開とし、モータ駆動式の再循環ポンプ14により
蒸気発生器1内に気水分向1器10内で分離された水を
再循環する。The steam-driven water supply pump 6 becomes difficult to operate as steam decreases, so when the separated water is stored in the steam-water separator 10 and the water level rises to a certain extent, the valve 17 is closed. The water separated in the steam/water director 10 is recirculated into the steam generator 1 by a motor-driven recirculation pump 14.
づなわら、ト記説明のこの実施例の崩壊熱除去運転方法
では、蒸気発生器1の出口側液体ナトリウム温度および
その温度変化率を監視しながら、給水流量を調整し、ま
た、再i!i!i liシステムの気水分離器10によ
って分離され蓄えられた水が一定の水位に達した後は、
蒸気駆動式の給水ポンプ6に替えて、モータ駆動式の再
循環ポンプ1/1を使い、この水を蒸気発生器内に再循
環するので、1涯1熱蒸気源の喪失によりII水器から
の給水の急激な温度低下による蒸気発生器1の出口液体
すlヘリウムノズル部に加わる熱衝撃を大幅に緩和する
ことができる。In addition, in the decay heat removal operation method of this embodiment described in Section 3, the feed water flow rate is adjusted while monitoring the liquid sodium temperature on the outlet side of the steam generator 1 and its temperature change rate, and the re-i! i! After the water separated and stored by the steam separator 10 of the ili system reaches a certain level,
Instead of the steam-driven feed water pump 6, a motor-driven recirculation pump 1/1 is used to recirculate this water into the steam generator, so that due to the loss of one heat steam source per year, the water is removed from the II water heater. The thermal shock applied to the outlet liquid sl helium nozzle portion of the steam generator 1 due to the rapid temperature drop of the feed water can be significantly alleviated.
なお、この実施例の方法では、関数発生器21に蒸気発
生器1の入口)1タ体太1〜リウム温度を入力して給水
流量目標値を設定したが、本発明)ユかかる実施例に限
定されるものではなく、たとえば時間の関数等として給
水流量目標値を設定してもよいことはもちろんである。In the method of this embodiment, the feed water flow rate target value was set by inputting the inlet temperature of the steam generator 1 into the function generator 21, but the present invention) It goes without saying that the target value of the water supply flow rate may be set as a function of time, etc., without being limited thereto.
[発明の効果]
以上述べたように本発明の崩壊熱除去運転方法で)よ、
給水温度の急激な低下による蒸気発生蒸出ロ液体ノ1〜
1戸シムノスル部に加わる熱衝撃を緩和Jることかでき
、高速増殖炉プラン1への健全性おJ、び安全性か損わ
れることを防[LlJることかできる。[Effect of the invention] As described above, the decay heat removal operation method of the present invention)
Steam generation and evaporation liquid No. 1 due to sudden drop in feed water temperature
It is possible to alleviate the thermal shock applied to the single symnosule part and prevent damage to the integrity and safety of the Fast Breeder Reactor Plan 1.
第1図は本発明の一実施例の方法に用いる制御装置の1
14成を示リブ[1ツク図、第2図は第1図に承り11
制御装首を配置された高速増り偵炉プラントの配管系統
図、第3図(J、高速増殖炉プラン1〜の配室系統図で
ある。
1・・・・・・・・・蒸気発生器
2・・・・・・・・・液体す[・1戸ツム入口配管3・
・・・・・・・・)丙1ホナ(〜リウム出口配管4・・
・・・・・・・主蒸気配管
8・・・・・・・・・給水配色
10・・・・・・・・・気水分離器
20・・・・・・・・・制荀口a刹
21・・・・・・・・・関数発生器
22・・・・・・・・・温度監視装置
23・・・・・・・・・微分器FIG. 1 shows one of the control devices used in the method of one embodiment of the present invention.
Rib showing 14 formations [1st figure, 2nd figure is based on 11th figure]
Piping system diagram of a fast breeder reactor plant with control head arranged, Figure 3 (J, is a room layout system diagram of fast breeder reactor plan 1~. 1... Steam generation Container 2...Liquid tank [・1 unit inlet piping 3・
......) Hei 1 Hona (~Rium outlet piping 4...
......Main steam piping 8...Water supply color scheme 10...Steam water separator 20...Control port a 21...Function generator 22...Temperature monitoring device 23...Differentiator
Claims (1)
高温側に循環された液体ナトリウムを冷却して崩壊熱の
除去を行なう崩壊熱除去運転方法において、前記蒸気発
生器に復水器から給水するとともに、前記蒸気発生器内
で発生する蒸気を再循環システム内の気水分離器に導入
し、この気水分離器により分離された水を前記蒸気発生
器に再循環し、かつ、前記蒸気発生器の液体ナトリウム
出口測温度および温度変化率を監視し、この液体ナトリ
ウム出口側温度および温度変化率がぞれぞれあらかじめ
設定された設定値を越えた場合には、それぞれの設定値
からの偏差に応じて前記復水器からの給水流量を減少さ
せることを特徴とする崩壊熱除去運転方法。(1) In a decay heat removal operation method in which water is supplied to the low temperature side of the steam generator and liquid sodium circulated to the high temperature side of the steam generator is cooled to remove decay heat, condensate water is supplied to the steam generator. At the same time, the steam generated in the steam generator is introduced into a steam-water separator in a recirculation system, and the water separated by the steam-water separator is recycled to the steam generator, and , the liquid sodium outlet temperature and temperature change rate of the steam generator are monitored, and if the liquid sodium outlet side temperature and temperature change rate exceed respective preset set values, the respective settings are changed. A decay heat removal operating method characterized in that the flow rate of water supplied from the condenser is reduced in accordance with the deviation from the value.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP60269594A JPS62129791A (en) | 1985-11-29 | 1985-11-29 | Decay-heat removing operating method |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP60269594A JPS62129791A (en) | 1985-11-29 | 1985-11-29 | Decay-heat removing operating method |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS62129791A true JPS62129791A (en) | 1987-06-12 |
Family
ID=17474534
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP60269594A Pending JPS62129791A (en) | 1985-11-29 | 1985-11-29 | Decay-heat removing operating method |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS62129791A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2012013558A (en) * | 2010-07-01 | 2012-01-19 | Hitachi-Ge Nuclear Energy Ltd | Isolation cooling system of nuclear power plant |
-
1985
- 1985-11-29 JP JP60269594A patent/JPS62129791A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2012013558A (en) * | 2010-07-01 | 2012-01-19 | Hitachi-Ge Nuclear Energy Ltd | Isolation cooling system of nuclear power plant |
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