JPH083555B2 - Boiling water nuclear power plant - Google Patents

Boiling water nuclear power plant

Info

Publication number
JPH083555B2
JPH083555B2 JP62070704A JP7070487A JPH083555B2 JP H083555 B2 JPH083555 B2 JP H083555B2 JP 62070704 A JP62070704 A JP 62070704A JP 7070487 A JP7070487 A JP 7070487A JP H083555 B2 JPH083555 B2 JP H083555B2
Authority
JP
Japan
Prior art keywords
water
hydrogen
reactor
oxygen
steam
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
JP62070704A
Other languages
Japanese (ja)
Other versions
JPS63236997A (en
Inventor
政人 小林
克己 大角
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
Original Assignee
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 Ltd filed Critical Hitachi Ltd
Priority to JP62070704A priority Critical patent/JPH083555B2/en
Publication of JPS63236997A publication Critical patent/JPS63236997A/en
Publication of JPH083555B2 publication Critical patent/JPH083555B2/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
    • 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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  • Agricultural Chemicals And Associated Chemicals (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、沸騰水型原子力発電所に係り、特に、その
原子炉一次冷却材の溶存酸素濃度制御のために系統構成
に関するものである。
Description: TECHNICAL FIELD The present invention relates to a boiling water nuclear power plant, and more particularly to a system configuration for controlling the dissolved oxygen concentration of the reactor primary coolant.

〔従来の技術〕[Conventional technology]

沸騰水型原子炉では、原子炉一次冷却材としての水の
一部が、炉心部で放射線照射を受けて、酸素と水素とに
分解する。この酸素は、原子炉冷却材の沸騰により発生
する蒸気とともに原子炉圧力容器外に持ち出される。し
かし、一部が原子炉圧力容器内の一次冷却材(以下、炉
水という)に残留するため、炉水の溶存酸素濃度が百pp
bとなる。この残留酸素は、原子炉一次系構成材料の腐
食を促進する可能性があるために、この酸素を低減する
目的で、従来は、特開昭57−1994号に記載のように、原
子炉給水に水素を注入していた。
In a boiling water reactor, a part of water as a reactor primary coolant is irradiated with radiation in the core part and decomposes into oxygen and hydrogen. This oxygen is carried out of the reactor pressure vessel together with steam generated by boiling of the reactor coolant. However, part of the residual oxygen remains in the primary coolant in the reactor pressure vessel (hereinafter referred to as reactor water), and the dissolved oxygen concentration in the reactor water is 100 pp.
b. This residual oxygen may accelerate the corrosion of the primary constituent materials of the reactor, and therefore, for the purpose of reducing this oxygen, conventionally, as described in JP-A-57-1994, the reactor feed water was used. Was being injected with hydrogen.

〔発明が解決しようとする問題点〕[Problems to be solved by the invention]

注入した水素は、炉心の沸騰部において炉水が分解し
て発生した水素および酸素とともに、蒸気側に移行す
る。これら蒸気中の水素と酸素は、最終的に回収された
後、水素−酸素再結合器で水に戻される。したがつて、
炉水の溶存酸素を常に低く制御するためには、常に系外
から給水に水素を注入する必要があつた。
The injected hydrogen moves to the steam side together with hydrogen and oxygen generated by the decomposition of the reactor water in the boiling portion of the core. The hydrogen and oxygen in these vapors are finally recovered and then returned to water in a hydrogen-oxygen recombiner. Therefore,
In order to constantly control the dissolved oxygen in the reactor water to a low level, it was always necessary to inject hydrogen into the feed water from outside the system.

また、上述の再結合器入口の水素と酸素との流量の関
係は、水と組成に関する化学量論比、すなわち体積流量
比で2:1に対して、注入水素分だけ過剰となる。これを
水に戻すには、給水に注入する水素に対して、水の化学
量論比に対応する酸素を再結合器入口側に注入する必要
があつた。それら水素と酸素は系外に排出していた。
Further, the above-mentioned flow rate relationship between hydrogen and oxygen at the inlet of the recombiner is excessive by the amount of injected hydrogen with respect to the stoichiometric ratio relating to water and composition, that is, the volume flow rate ratio of 2: 1. In order to return this to water, it was necessary to inject oxygen corresponding to the stoichiometric ratio of water into the recombiner inlet side with respect to hydrogen injected into the feed water. The hydrogen and oxygen were discharged outside the system.

したがつて、給水に注入する水素と再結合器に注入す
る酸素とを常に供給しなければならず、その費用が膨大
になる欠点があつた。
Therefore, the hydrogen to be injected into the feed water and the oxygen to be injected into the recombiner have to be constantly supplied, which has a drawback that the cost thereof becomes huge.

本発明の目的は、水素の注入と酸素の注入により炉水
の溶存酸素濃度の低減と上昇が可能となり、炉水の溶存
酸素濃度を任意に調節することができる沸騰水型原子力
発電所を提供することである。
An object of the present invention is to provide a boiling water nuclear power plant capable of reducing and increasing the dissolved oxygen concentration of reactor water by injecting hydrogen and oxygen, and capable of arbitrarily adjusting the dissolved oxygen concentration of reactor water. It is to be.

〔問題点を解決するための手段〕[Means for solving problems]

本発明は、上記目的を達成するために、原子炉圧力容
器で発生しタービンで仕事をした蒸気を水に戻す復水器
と、戻された前記水を加熱し前記圧力容器に供給する給
水加熱器と、前記蒸気中の酸素および水素を回収し化学
的に結合させて水にする再結合器とを有する沸騰水型原
子力発電所において、再結合器で結合しなかった余分な
気体を復水器下流の復水配管に戻すオフガス戻りライン
を設け、復水器から給水加熱器までの間に水素注入装置
及び酸素注入装置を設けた沸騰水型原子力発電所を提案
するものである。
The present invention, in order to achieve the above object, a condenser for returning steam generated in a reactor pressure vessel and worked in a turbine to water, and feed water heating for heating the returned water and supplying it to the pressure vessel. In a boiling water nuclear power plant having a reactor and a recombiner that recovers oxygen and hydrogen in the steam and chemically combines them into water, the excess gas that was not combined by the recombiner is condensed. We propose a boiling water nuclear power plant equipped with an off-gas return line that returns to the condensate pipe downstream of the reactor, and a hydrogen injector and an oxygen injector between the condenser and the feed water heater.

また、前記再結合器の入口と出口とを短絡する開閉可
能な配管を設けても良い。
In addition, a pipe that can be opened and closed to short-circuit the inlet and outlet of the recombiner may be provided.

〔作用〕[Action]

再係合器出口と復水器下流とを結ぶラインは、再結合
器で酸素と再結合されないで出口から出る水素を、給水
または復水を経て炉水に導く。復水器下流に設けた水素
および酸素の注入設備は、炉水の溶存酸素をより低くす
るために水素を注入し、より高くするために酸素を注入
するためのものである。すなわち、水素を注入すると、
この水素が炉心部における水の放射線分解を抑制し、炉
水中の溶存酸素を低減する。このとき、蒸気側へ移行し
再結合器に入る水素は、同酸素と再結合器で化合し水と
なるが、注入した水素が過剰分として残り、再結合器出
口から復水器下流に戻される。この時点で水素注入を停
止すると、それまでに注入した水素が炉水と蒸気の間で
常に循環し、炉心部での水の放射線分解を常に抑え、炉
心の溶存酸素を低く維持する。
The line connecting the outlet of the re-engager and the downstream of the condenser guides hydrogen, which is not recombined with oxygen in the re-combiner and exits from the outlet, to the reactor water via feed water or condensate. The hydrogen and oxygen injection facility provided downstream of the condenser is for injecting hydrogen to lower the dissolved oxygen in the reactor water and injecting oxygen to increase it. That is, when hydrogen is injected,
This hydrogen suppresses radiolysis of water in the core and reduces dissolved oxygen in the reactor water. At this time, the hydrogen that migrates to the steam side and enters the recombiner is combined with the same oxygen in the recombiner to form water, but the injected hydrogen remains as an excess and is returned from the recombiner outlet to the downstream of the condenser. Be done. If the hydrogen injection is stopped at this point, the hydrogen injected up to that point always circulates between the reactor water and the steam, and the radiolysis of water in the core is always suppressed, and the dissolved oxygen in the core is kept low.

プラント停止時等には、余分な水素は防爆上の観点等
からは少ないほうが良い。前記炉心の溶存酸素を低く維
持していた状態から、余分な水素を減らすために、炉水
の溶存酸素を高くする場合、酸素注入設備から酸素を注
入する。この場合、給水または復水では、前記の系内を
循環する水素と注入酸素とが共存するが、これらは原子
炉圧力容器に入るとすぐお互いに化合し水となる。すな
わち、注入酸素により系内を循環する水素が減じられる
が、この循環水素が所定量まで減つた時点で酸素注入を
停止すると、炉水の溶存酸素濃度はその循環する水素量
に対応する値まで増加し、その値に維持される。
When the plant is stopped, etc., it is better that the excess hydrogen is small from the viewpoint of explosion protection. When the dissolved oxygen in the reactor core is kept low to increase the dissolved oxygen in the reactor water in order to reduce excess hydrogen, oxygen is injected from the oxygen injection equipment. In this case, in feed water or condensate, hydrogen and injected oxygen that co-exist in the system coexist, but when they enter the reactor pressure vessel, they combine with each other to form water. That is, the hydrogen circulating in the system is reduced by the injected oxygen, but if the oxygen injection is stopped when the circulating hydrogen decreases to a predetermined amount, the dissolved oxygen concentration in the reactor water reaches the value corresponding to the circulating hydrogen amount. Increased and maintained at that value.

このように復水または給水に水素と酸素とが混在する
と、これが化合した水になつたとき残留する分の過剰水
素が炉心部の水の放射線分解をその量に応じて抑制する
ことになる。したがつて、再結合器をバイパスする配管
に設けた弁を開き、蒸気中に移行した水素と酸素とをそ
のまま復水または給水に戻しても、炉心の溶存酸素濃度
を安定に制御でき、しかも再結合器の運転を止めること
が可能である。
When hydrogen and oxygen are mixed in the condensate water or the feed water, excess hydrogen that remains when the condensed water becomes combined water suppresses radiolysis of the water in the core according to the amount. Therefore, even if the valve provided in the pipe bypassing the recombiner is opened and the hydrogen and oxygen transferred into the steam are returned to the condensate or feed water as they are, the dissolved oxygen concentration in the core can be stably controlled, and It is possible to stop the operation of the recombiner.

〔実施例〕〔Example〕

次に、図面を参照して本発明の一実施例を説明する。 Next, an embodiment of the present invention will be described with reference to the drawings.

第1図は、本発明による沸騰水型原子力発電所の系統
構成の概略を示す図である。図において、1は原子炉圧
力容器、2はその蒸気を取り出す主蒸気配管、3はター
ビン、4は復水器、5は復水ポンプ、6は復水配管、7
は給水加熱器、8はその給水配管、9はオフガスライ
ン、10は蒸気により駆動されるエゼクタ、11はエゼクタ
10に蒸気を供給するエデクタ駆動ライン、12は再結合
器、13はオフガス復水器、14はオフガス戻りライン、15
はバイパス配管、16はその途中に設けた弁、17は水素ま
たは酸素の注入ライン、18は水素注入弁、19は水素ボン
ベ、20は酸素注入弁、21は酸素ボンベ、22は炉心、23は
気水分離器、24はシユラウド、25はダウンカマ、26は水
素濃度計、27は酸素濃度計である。
FIG. 1 is a diagram showing an outline of a system configuration of a boiling water nuclear power plant according to the present invention. In the figure, 1 is a reactor pressure vessel, 2 is a main steam pipe for taking out the steam, 3 is a turbine, 4 is a condenser, 5 is a condensate pump, 6 is a condensate pipe, and 7 is a condensate pipe.
Is a water heater, 8 is a water supply pipe, 9 is an off-gas line, 10 is an ejector driven by steam, and 11 is an ejector.
Eductor drive line for supplying steam to 10, 12 recombiner, 13 off gas condenser, 14 off gas return line, 15
Is a bypass pipe, 16 is a valve provided on the way, 17 is a hydrogen or oxygen injection line, 18 is a hydrogen injection valve, 19 is a hydrogen cylinder, 20 is an oxygen injection valve, 21 is an oxygen cylinder, 22 is a core, and 23 is A steam separator, 24 is a shroud, 25 is a downcomer, 26 is a hydrogen concentration meter, and 27 is an oxygen concentration meter.

原子炉圧力容器1で発生した蒸気は、主蒸気配管2に
よりタービン3に導かれ、これを駆動し、復水器4で凝
縮され、ポンプ5により加圧され、復水配管6と給水加
熱器7と給水配管8とを経て、原子炉圧力容器1に戻さ
れる。
The steam generated in the reactor pressure vessel 1 is guided to the turbine 3 by the main steam pipe 2, drives the turbine 3, is condensed by the condenser 4, is pressurized by the pump 5, and is condensed by the condenser pipe 6 and the feed water heater. It is returned to the reactor pressure vessel 1 via 7 and the water supply pipe 8.

蒸気中に含まれる蒸気,水素等の非凝縮性ガス成分
は、エデクタ駆動ライン11からの蒸気で駆動されるエゼ
クタ10により、復水器4からオフガスライン9に回収さ
れた後、再結合器12において酸素と水素とが化合し、水
となる。蒸気はオフガス復水器13により水にされ、オフ
ガス戻りライン14から復水配管6に戻される。再結合器
12の入口および出口は、バイパス配管15で結ばれ、弁16
を開ければ再結合器12がバイパスされる。
Non-condensable gas components such as steam and hydrogen contained in the steam are recovered from the condenser 4 to the off-gas line 9 by the ejector 10 driven by the steam from the ejector drive line 11, and then recombined 12 At, oxygen and hydrogen combine to form water. The steam is turned into water by the offgas condenser 13, and is returned to the condensate pipe 6 from the offgas return line 14. Recombiner
The 12 inlets and outlets are connected by bypass piping 15 and valve 16
Opening bypasses the recombiner 12.

復水器6には、注入ライン17が接続されており、水素
注入弁18または酸素注入弁20を開くと、それぞれ水素ま
たは酸素が復水中に注入される。
An injection line 17 is connected to the condenser 6, and when the hydrogen injection valve 18 or the oxygen injection valve 20 is opened, hydrogen or oxygen is injected into the condensate, respectively.

炉水の溶存酸素濃度の制御は、以下のように行う。ま
ず、水素注入弁18を開き、復水配管6に水素を注入す
る。この水素は、給水系により原子炉圧力容器1内に戻
され、以下のように、炉水の溶存酸素濃度を低減する。
沸騰水型原子炉では、炉水22で炉水が沸騰して蒸気とな
る。気水分離器23では、炉水と蒸気が分離され、蒸気は
主蒸気配管2に導かれる。炉水は、炉心22を取り囲むシ
ユラウド24と原子炉圧力容器1との間のダウンカマ25を
下降し、再び炉心22に導かれるように循環する。注入さ
れた水素は、ダウンカマ25において、炉心22から放射さ
れる放射線の効果により炉水中に溶存した酸素と化合し
て水になる。さらに、残つた水素は、炉心22に到達し、
ここでの水の放射線分解を抑制する。
The dissolved oxygen concentration in the reactor water is controlled as follows. First, the hydrogen injection valve 18 is opened, and hydrogen is injected into the condensate pipe 6. This hydrogen is returned to the reactor pressure vessel 1 by the water supply system and reduces the dissolved oxygen concentration of the reactor water as follows.
In a boiling water reactor, the reactor water is boiled by the reactor water 22 to become steam. In the steam separator 23, the reactor water and steam are separated, and the steam is guided to the main steam pipe 2. The reactor water circulates down the downcomer 25 between the shell 24 surrounding the core 22 and the reactor pressure vessel 1, and is guided to the core 22 again. The injected hydrogen is combined with oxygen dissolved in the reactor water into water in the downcomer 25 due to the effect of radiation emitted from the core 22. Further, the remaining hydrogen reaches the core 22,
Suppress radiolysis of water here.

水素による炉水の溶存酸素低減効果は、第2図の曲線
Aで示される。給水中の水素濃度を増大させると、炉水
中の溶存酸素濃度が薄くなる。炉水溶存酸素濃度の具体
的制御は、以下のように実行する。まず、第2図に示す
関係から、所定の溶存酸素濃度に対応する給水中水素濃
度を読み取り、これに対応する水素を注入する。注入し
た水素は、その量がそのまま、主蒸気配管2,オフガスラ
イン9,およびオフガス戻りライン14を経て、若干の時間
遅れをもつて復水配管6に戻される。この時間遅れは、
通常数10秒から数分である。復水配管6への注入ライン
17の接続点よりも上流側に設けた水素濃度計26により注
入水素が戻つたことが確認された時点で、水素注入弁18
を閉じる。この状態で注入した水素は、原子炉圧力容器
1,主蒸気配管2,オフガスライン9,オフガス戻りライン1
4,復水配管6および給水配管8の経路で、常に系内を循
環しており、炉水の溶存酸素濃度を当初設定の値に維持
する。
The effect of hydrogen for reducing dissolved oxygen in reactor water is shown by curve A in FIG. Increasing the hydrogen concentration in the feedwater dilutes the dissolved oxygen concentration in the reactor water. The concrete control of the concentration of dissolved oxygen in the furnace is carried out as follows. First, from the relationship shown in FIG. 2, the hydrogen concentration in the feed water corresponding to the predetermined dissolved oxygen concentration is read, and hydrogen corresponding to this is injected. The injected hydrogen is returned to the condensate pipe 6 with a slight time delay through the main steam pipe 2, the off-gas line 9 and the off-gas return line 14 in the same amount. This time delay is
It usually takes a few tens of seconds to a few minutes. Injection line to condensate pipe 6
When the hydrogen concentration meter 26 provided upstream of the connection point of 17 confirmed that the injected hydrogen had returned, the hydrogen injection valve 18
Close. Hydrogen injected in this state is the reactor pressure vessel.
1, main steam pipe 2, off-gas line 9, off-gas return line 1
4. The condensate pipe 6 and the feed water pipe 8 are constantly circulating in the system to maintain the dissolved oxygen concentration in the reactor water at the initially set value.

このような状態で、炉水溶存酸素濃度をさらに減少ま
たは増大させる操作は、以下のようになされる 溶存酸素濃度をさらに低減させるためには、この溶存
酸素濃度設定値から対応する給水水素濃度値を読み取
り、この値と水素濃度計26の読みの差に相当する水素を
注入し、その後、水素濃度計26の読みが第2図から求め
た水素濃度が等しくなつたとき、水素注入弁18を閉じて
水素の注入を停止する。
In such a state, the operation to further reduce or increase the dissolved oxygen concentration in the furnace is performed as follows.To further reduce the dissolved oxygen concentration, in order to further reduce the dissolved oxygen concentration set value, Is read, and hydrogen corresponding to the difference between this value and the reading of the hydrogen concentration meter 26 is injected. After that, when the readings of the hydrogen concentration meter 26 show that the hydrogen concentrations obtained from FIG. 2 are equal, the hydrogen injection valve 18 is turned on. Close and stop hydrogen injection.

次に、溶存酸素濃度を増大させる方法について述べ
る。この場合も、第2図から目標とする炉水溶存酸素濃
度に対する給水中水素濃度を読み取り、その濃度と水素
濃度計26の読みの差を求める。その差に対し、水の化学
量論比に対応する濃度の酸素を注入する。注入した酸素
は、ダウンカマ25で系内を循環する水素と化合して水と
なり、この水素を消費する。水素濃度計26の読みが第2
図から読み取つた給水中の水素濃度に等しくなつた時点
で酸素注入弁20を閉じ、酸素注入を停止する。
Next, a method for increasing the dissolved oxygen concentration will be described. Also in this case, the hydrogen concentration in the feed water with respect to the target oxygen concentration in the reactor water is read from FIG. To the difference, oxygen is injected at a concentration corresponding to the stoichiometric ratio of water. The injected oxygen is combined with hydrogen circulating in the system in the downcomer 25 to become water, and this hydrogen is consumed. The reading of the hydrogen concentration meter 26 is second
The oxygen injection valve 20 is closed and the oxygen injection is stopped when the hydrogen concentration in the feed water becomes equal to that read from the figure.

なお、以上の制御方式においては、再結合器12を使用
しないでバイパスできる。すなわち、弁16を開き、バイ
パス配管15により、再結合器12をバイパスする。この場
合、炉水の溶存酸素濃度を制御するには、上記方法にお
ける水素濃度計26の読みを、水素濃度計26の読みから酸
素濃度計27の読み対して水の化学量論比で対応する水素
の濃度値を差し引いた値に読み換えれば良い。
In the above control method, the bypass can be performed without using the recombiner 12. That is, the valve 16 is opened and the recombiner 12 is bypassed by the bypass pipe 15. In this case, in order to control the dissolved oxygen concentration of the reactor water, the reading of the hydrogen concentration meter 26 in the above method is corresponded to the reading of the oxygen concentration meter 27 from the reading of the hydrogen concentration meter 26 by the stoichiometric ratio of water. It can be read as a value obtained by subtracting the hydrogen concentration value.

〔発明の効果〕〔The invention's effect〕

本発明によれば、炉水の溶存酸素濃度の制御におい
て、系外から水素および酸素を常に供給している必要は
なく、これら水素及び酸素の膨大な費用を削減できる。
また水素の注入と酸素の注入により炉水の溶存酸素濃度
を任意に調節することができる。
According to the present invention, in controlling the dissolved oxygen concentration of reactor water, it is not necessary to constantly supply hydrogen and oxygen from outside the system, and it is possible to reduce enormous costs of hydrogen and oxygen.
Further, the dissolved oxygen concentration in the reactor water can be arbitrarily adjusted by injecting hydrogen and oxygen.

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

第1図は本発明による沸騰水型原子力発電所の系統構成
の概略図、第2図は第1図実施例の給水中水素濃度と炉
水溶存酸素濃度との関係を示す図である。 1……原子炉圧力容器、3……タービン、4……復水
器、6……復水配管、7……給水加熱器、8……給水配
管、10……エゼクタ、12……再結合器、13……オフガス
復水器、14……オフガス戻りライン、15……バイパス配
管、19……水素ボンベ、21……酸素ボンベ。
FIG. 1 is a schematic diagram of the system configuration of a boiling water nuclear power plant according to the present invention, and FIG. 2 is a diagram showing the relationship between the hydrogen concentration in feed water and the concentration of dissolved oxygen in reactor water in the embodiment of FIG. 1 ... Reactor pressure vessel, 3 ... Turbine, 4 ... Condenser, 6 ... Condensation pipe, 7 ... Feed water heater, 8 ... Feed pipe, 10 ... Ejector, 12 ... Rejoin Vessel, 13 …… off gas condenser, 14 …… off gas return line, 15 …… bypass piping, 19 …… hydrogen cylinder, 21 …… oxygen cylinder.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】原子炉圧力容器で発生しタービンで仕事を
した蒸気を水に戻す復水器と、戻された前記水を加熱
し、前記圧力容器に供給する給水加熱器と、前記蒸気中
の酸素および水素を回収し化学的に結合させて水にする
再結合器とを有する沸騰水型原子力発電所において、 前記再結合器で結合しなかった余分な気体を前記復水器
下流の復水配管に戻すオフガス戻りラインを設け、かつ 前記復水器から前記給水加熱器までの間に炉水中の溶存
酸素濃度を低減させるために水素を原子炉に供給する水
素注入装置及び前記溶存酸素濃度を低減させる度合いを
調整するために酸素を原子炉に供給する酸素注入装置を
設けると共に、前記再結合器の入口と出口とを短絡する
開閉可能な配管を設けたことを特徴とする沸騰水型原子
力発電所。
1. A condenser for returning steam generated in a reactor pressure vessel and worked in a turbine to water, a feed water heater for heating the returned water and supplying the water to the pressure vessel, and the steam in the steam. In a boiling water nuclear power plant having a recombiner that recovers oxygen and hydrogen of the above and chemically combines them into water, the excess gas that was not combined in the recombiner is recovered in the downstream of the condenser. An off-gas return line for returning to the water pipe is provided, and a hydrogen injection device for supplying hydrogen to the reactor to reduce the dissolved oxygen concentration in the reactor water between the condenser and the feed water heater and the dissolved oxygen concentration. Is provided with an oxygen injection device for supplying oxygen to the reactor in order to adjust the degree to reduce the boiling water type, which is provided with a pipe that can be opened and closed to short-circuit the inlet and outlet of the recombiner. Nuclear power plant.
JP62070704A 1987-03-25 1987-03-25 Boiling water nuclear power plant Expired - Lifetime JPH083555B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62070704A JPH083555B2 (en) 1987-03-25 1987-03-25 Boiling water nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62070704A JPH083555B2 (en) 1987-03-25 1987-03-25 Boiling water nuclear power plant

Publications (2)

Publication Number Publication Date
JPS63236997A JPS63236997A (en) 1988-10-03
JPH083555B2 true JPH083555B2 (en) 1996-01-17

Family

ID=13439251

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62070704A Expired - Lifetime JPH083555B2 (en) 1987-03-25 1987-03-25 Boiling water nuclear power plant

Country Status (1)

Country Link
JP (1) JPH083555B2 (en)

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59220687A (en) * 1983-05-30 1984-12-12 株式会社日立製作所 Corrosion environment control equipment for direct cycle light water reactor primary cooling system
JPS6048716A (en) * 1983-08-25 1985-03-16 シャープ株式会社 Rice cooker
JPS6168599A (en) * 1984-09-13 1986-04-08 株式会社東芝 Gas waste treater
JPS61104298A (en) * 1984-10-26 1986-05-22 日本原子力事業株式会社 Radioactivity accumulation reducer for nuclear reactor primary cooling system
JPS61290398A (en) * 1985-06-19 1986-12-20 株式会社日立製作所 Hydrogen injection system in boiling water type nuclear power facility

Also Published As

Publication number Publication date
JPS63236997A (en) 1988-10-03

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