JPH03128488A - Nuclear reactor emergency stopping device - Google Patents

Nuclear reactor emergency stopping device

Info

Publication number
JPH03128488A
JPH03128488A JP1103373A JP10337389A JPH03128488A JP H03128488 A JPH03128488 A JP H03128488A JP 1103373 A JP1103373 A JP 1103373A JP 10337389 A JP10337389 A JP 10337389A JP H03128488 A JPH03128488 A JP H03128488A
Authority
JP
Japan
Prior art keywords
scram
detector
logic circuit
emergency
reactor
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.)
Granted
Application number
JP1103373A
Other languages
Japanese (ja)
Other versions
JP2740000B2 (en
Inventor
Masahiko Fujii
正彦 藤井
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
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP1103373A priority Critical patent/JP2740000B2/en
Publication of JPH03128488A publication Critical patent/JPH03128488A/en
Application granted granted Critical
Publication of JP2740000B2 publication Critical patent/JP2740000B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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)

Abstract

PURPOSE:To improve the reliability of an emergency stopping function and to easily introduce the device in an existent plant by operating an emergency stop valve which is provided later even by an independent detector and a logic circuit, and stopping a nuclear reactor in emergency. CONSTITUTION:The device is provided with the detector 14 independent of a detector 1 and detection signals as to parameters of high reactor pressure and low reactor water level which become extremely severe to handle in case of a failure in scramming are inputted to a substitute control rod insertion logic circuit 15 independent of a scram logic circuit 2 to generate a substitute control rod insertion signal S2 completely independent of a scram signal S1; and the existent emergency valve 13 which is provided afterward is put in operation to discharge air from a scram air header 11, and the control rod is inserted in emergency. Consequently, the scram logic circuit 2 and detector 1 are made redundant and diversed, so the reliability of the emergency stopping device due to them is improved greatly. Further, the device can be introduced in the existent plant only by providing the relatively inexpensive logic circuit and detector additionally.

Description

【発明の詳細な説明】 [発明の目的コ (産業上の利用分野) 本発明は原子炉を緊急停止させる原子炉緊急停止装置に
関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention (Industrial Application Field) The present invention relates to a nuclear reactor emergency shutdown device for emergency shutdown of a nuclear reactor.

(従来の技術) 原子炉緊急停止装置は原子炉の安全性を損うおそれのあ
る事態が発生あるいは発生が予想される場合に、原子炉
を保護するために全制御棒を緊急挿入(スクラム)させ
る機能を備えている。
(Prior technology) A nuclear reactor emergency shutdown system automatically inserts all control rods (scram) to protect the reactor when a situation that may impair the safety of the reactor occurs or is expected to occur. It has the function to

以下、従来の原子炉緊急停止装置を第2図の概略構成図
を参照して説明する。
Hereinafter, a conventional nuclear reactor emergency shutdown system will be explained with reference to the schematic diagram of FIG. 2.

第2図では原子炉の制御棒1本に対する制御棒駆動機構
とその緊急停止装置しか示されていないが、実際には制
御棒は複数本装備されており、信頼性向上のために多重
化や冗長化が行なわれている。
Although Figure 2 only shows the control rod drive mechanism and its emergency stop device for one control rod in a nuclear reactor, in reality, multiple control rods are installed, and multiple control rods are used to improve reliability. Redundancy is being implemented.

一般に、原子炉の安全性を損うおそれのある事態の発生
あるいは発生の予想は、原子炉の安全性に関して重要な
パラメータがある設定値を越えるか否かによって判断さ
れる。この重要なパラメータは検出器1によって常時監
視されている。検出器1の検出信号はスクラム論理回路
2に送られ、スクラム動作の必要性が判断され、スクラ
ムが必要な場合にはスクラム信号S1が生成される。
In general, the occurrence or prediction of the occurrence of a situation that may impair the safety of a nuclear reactor is determined based on whether or not an important parameter regarding the safety of a nuclear reactor exceeds a certain set value. This important parameter is constantly monitored by the detector 1. The detection signal of the detector 1 is sent to a scram logic circuit 2 to determine whether a scram operation is necessary, and if a scram operation is necessary, a scram signal S1 is generated.

まず、制御棒の緊急挿入動作について説明する。First, the emergency insertion operation of the control rod will be explained.

水圧制御ユニット3のスクラム入口弁4およびスクラム
出口弁5は通常運転時には閉じているが、スクラム時に
はスクラム入口弁4が開き、アキュムレータ6から制御
棒駆動機構7のシリンダ部8に高圧の駆動水が送られる
とともに、スクラム出口弁5が開き制御棒駆動機構7の
シリンダ上部9の駆動水はスクラム排出容器10に排出
される。したがって、制御棒駆動機構7は下方から上方
に向かって原子炉内に挿入される。この水圧制御ユニッ
ト3および制御棒駆動機構7は、各制御棒毎に具備され
ている。
The scram inlet valve 4 and the scram outlet valve 5 of the water pressure control unit 3 are closed during normal operation, but during scram, the scram inlet valve 4 opens and high-pressure drive water flows from the accumulator 6 to the cylinder section 8 of the control rod drive mechanism 7. At the same time, the scram outlet valve 5 opens and the drive water in the cylinder upper part 9 of the control rod drive mechanism 7 is discharged into the scram discharge container 10. Therefore, the control rod drive mechanism 7 is inserted into the reactor from the bottom to the top. The hydraulic control unit 3 and control rod drive mechanism 7 are provided for each control rod.

次に、スクラム人口弁4およびスクラム出口弁5の開閉
制御について説明する。
Next, the opening/closing control of the scram population valve 4 and the scram outlet valve 5 will be explained.

スクラム人口弁46よびスクラム出口弁5は空気作動で
あり、空気圧が喪失すると開く設計となっている。常時
は計装用空気がスクラム・エア・ヘッダー11に供給さ
れ、この空気圧により前記スクラム人口弁4およびスク
ラム出口弁5の閉状態が維持されている。
The scram population valve 46 and scram outlet valve 5 are pneumatically operated and are designed to open upon loss of air pressure. Instrument air is normally supplied to the scram air header 11, and this air pressure keeps the scram population valve 4 and the scram outlet valve 5 closed.

前記したようにスクラム信@S1が発生すると、各制御
棒に固有のスクラムパイロット弁12が計装用空気の供
給側を遮断するとともに、排気側を開くように動作し、
スクラム・エア・ヘッダー11内の空気が排気されるの
で、空気圧が喪失し、スクラム人口弁4およびスクラム
出口弁5が開き、制御棒駆動機構が動作し制御棒が緊急
挿入される。
As described above, when a scram signal @S1 occurs, the scram pilot valve 12 unique to each control rod operates to shut off the instrument air supply side and open the exhaust side.
As the air in the scram air header 11 is vented, air pressure is lost, the scram population valve 4 and the scram outlet valve 5 open, the control rod drive mechanism operates and the control rod is emergency inserted.

ざらに、スクラムパイロット弁12とは独立に、全制御
棒に共通の後備緊急停止弁13が設けられており、この
後備緊急停止弁13もスクラム信号S1でスクラム・エ
ア・ヘッダー11の排気を行い、スクラム動作を行うこ
とができる。
Roughly speaking, a backup emergency stop valve 13 common to all control rods is provided independently of the scram pilot valve 12, and this backup emergency stop valve 13 also exhausts the scram air header 11 in response to the scram signal S1. , can perform Scrum operations.

以上説明したように、原子炉緊急停止装置はスクラム信
号S1により、スクラム・エア・ヘッダー11内の空気
を排気することにより、制御棒を緊急挿入して原子炉内
の核分裂反応を停止させる。
As explained above, the nuclear reactor emergency shutdown device uses the scram signal S1 to exhaust the air in the scram air header 11, thereby emergencyly inserting the control rods and stopping the nuclear fission reaction in the reactor.

一方、前記したように原子炉緊急停止装置は、原子炉の
安全性を損うおそれのある事態に、原子炉を保護するた
めに全制御棒を緊急挿入(スクラム)させることである
が、原子炉緊急停止装置が機能を喪失した場合には、そ
の後の事故進展が非常に速いため、運転員が他の系統を
用いて事故を収束させ、安全性を確保するための時間的
余裕がない場合がある。万一、このような事態が発生し
た場合には、原子炉の安全性が守れず、大事故に至る可
能性が考えられる。
On the other hand, as mentioned above, the reactor emergency shutdown system is used to urgently insert all control rods (scram) in order to protect the reactor in a situation where the safety of the reactor may be compromised. If the reactor emergency shutdown system loses its function, the accident progresses so quickly that operators do not have time to use other systems to bring the accident under control and ensure safety. There is. If such a situation were to occur, the safety of the nuclear reactor could not be maintained and a major accident could occur.

このため、原子炉緊急停止装置は高度に多重化。For this reason, reactor emergency shutdown equipment is highly multiplexed.

冗長化され、非常に信頼性が高くなるように設計されて
おり、このような事態の発生確率は非常に小さくはある
が、故障時の影響を考慮した場合には、必ずしも他の原
因で発生するリスクに比べて無視し得るものではなくな
る可能性もある。
The system is designed to be redundant and highly reliable, and although the probability of such an event occurring is very small, when considering the effects of a failure, it is not necessarily the case that it occurs due to other causes. There is also a possibility that the risks may no longer be negligible compared to the risks involved.

この原子炉緊急停止装置の機能喪失に至る可能性の最も
大きな故障原因は、スクラム論理回路2の故障であり、
次いで検出器1の故障である。したがって、原子炉緊急
停止機能の信頼性をより一層向上させるためには、スク
ラム論理回路2あるいは検出器1とは、完全に独立した
論理回路および検出器を設けることが必要である。
The most likely cause of failure that will lead to loss of functionality of this reactor emergency shutdown device is a failure of the scram logic circuit 2.
Next is the failure of the detector 1. Therefore, in order to further improve the reliability of the reactor emergency shutdown function, it is necessary to provide a logic circuit and a detector completely independent of the scram logic circuit 2 or the detector 1.

このような設備として、米国などでは代替制御棒挿入シ
ステムが開発されている。これは、前記したように、ス
クラムに失敗した場合に原子炉の安全性にとって、その
後の対処が非常に厳しくなるようなパラメータについて
、原子炉緊急停止装置とは完全に独立した検出器14、
代替制御棒挿入論理回路15を設けている。そして、原
子炉の安全性にとって非常に厳しい影響を及ぼすパラメ
ータについて、この代替制御棒挿入論理回路15で代替
制御棒挿入信号S2を生成し、これにより後備緊急停止
弁13と同じ機能を持つ独立した代替制御棒挿入弁16
を動作ざぜることにより、スクラム・エア・ヘッダー1
1の空気を排気し、制御棒の緊急挿入に対する信頼性を
向上させるものである。
As such equipment, alternative control rod insertion systems are being developed in the United States and other countries. As mentioned above, the detector 14, which is completely independent of the reactor emergency shutdown system, is used to detect parameters that would be extremely difficult to deal with for the safety of the reactor in the event of a scram failure.
An alternate control rod insertion logic circuit 15 is provided. Then, regarding the parameters that have a very severe effect on the safety of the reactor, the alternative control rod insertion logic circuit 15 generates an alternative control rod insertion signal S2, thereby creating an independent control rod insertion signal S2 that has the same function as the backup emergency stop valve 13. Alternative control rod insertion valve 16
Scram air header 1
This is to improve reliability for emergency insertion of control rods.

(発明が解決しようとする課題) ところで、上述のように原子炉緊急停止装置に加えて、
ざらに代替制御棒挿入システムを装備することは、制御
棒の緊急挿入の信頼性の向上に対しては非常に有効であ
るが、この代替制御棒挿入システムを既存プラントにフ
ィードバックして、追設する場合には、以下のような問
題点がある。
(Problem to be solved by the invention) By the way, in addition to the reactor emergency shutdown device as mentioned above,
Equipping Zara with an alternative control rod insertion system is very effective in improving the reliability of emergency control rod insertion, but this alternative control rod insertion system can be fed back to existing plants and added to the plant. If so, there are the following problems.

すなわち、制御棒挿入システムを既存プラントに追設す
る場合には、スクラム・エア・ヘッダー11に代替制御
棒挿入弁16を追設するためのプラント改造工事が必要
となり、これにはかなりの費用が必要となる。
In other words, when adding a control rod insertion system to an existing plant, plant modification work is required to add an alternative control rod insertion valve 16 to the scram air header 11, which requires considerable cost. It becomes necessary.

しかしながら、原子炉緊急停止装置の機能喪失に寄与す
る主要な要因は、後備緊急停止弁13の故障ではなくス
クラム論理回路2および検出器1の故障であり、またこ
の代替制御棒挿入弁16の追加工事は難しく、費用を要
する割りにはあまり信頼性向上に寄与しないという問題
点があった。
However, the main factor contributing to the loss of functionality of the reactor emergency shutdown system is not the failure of the backup emergency stop valve 13 but the failure of the scram logic circuit 2 and the detector 1, and the addition of this alternative control rod insertion valve 16. The problem was that construction was difficult and expensive, but it did not significantly improve reliability.

本発明は上記事情に鑑みてなされたもので、その目的は
、原子炉緊急停止機能の信頼性を著しく向上させること
ができ、しかも既設のプラントに容易に導入できる原子
炉緊急停止装置を提供することにある。
The present invention has been made in view of the above circumstances, and its purpose is to provide a nuclear reactor emergency shutdown device that can significantly improve the reliability of the nuclear reactor emergency shutdown function and can be easily introduced into existing plants. There is a particular thing.

[発明の構成] (課題を解決するための手段および作用)本発明は上記
目的を達成するために、原子炉のパラメータを検出する
検出器と、この検出器から得られた検出信号に基づいて
原子炉の緊急停止信号を生成する論理回路と、前記緊急
停止信号により各制御棒に固有の排気弁および全制御棒
に共通の後備緊急停止弁を動作させ空気ヘッダーの空気
を排気することにより制御棒を緊急挿入して原子炉を緊
急停止する原子炉緊急停止装置において、前記検出器と
は独立した検出器および前記論理回路とは独立した論理
回路を設け、この独立した検出器および論理回路によっ
ても前記後備緊急停止弁を動作させ原子炉を緊急停止さ
せるように構成したことを特徴とするものである。
[Structure of the Invention] (Means and Effects for Solving the Problems) In order to achieve the above object, the present invention provides a detector for detecting parameters of a nuclear reactor and a detection signal obtained from the detector. A logic circuit that generates an emergency stop signal for the reactor, and the emergency stop signal operates an exhaust valve specific to each control rod and a backup emergency stop valve common to all control rods to exhaust air from the air header. In a nuclear reactor emergency shutdown device that urgently stops a nuclear reactor by urgently inserting a rod, a detector independent of the above-mentioned detector and a logic circuit independent of the above-mentioned logic circuit are provided, and this independent detector and logic circuit The present invention is also characterized in that the backup emergency stop valve is operated to bring the reactor to an emergency stop.

本発明の原子炉緊急停止装置によれば、比較的安価な代
替制御棒挿入論理回路およびこれへの入力信号を監視す
る検出器のみを追加するだけで、既存プラントの原子炉
緊急停止装置の信頼性を安価で簡単な工事により大巾に
向上させることが可能となる。
According to the reactor emergency shutdown system of the present invention, by simply adding a relatively inexpensive alternative control rod insertion logic circuit and a detector that monitors the input signal thereto, the reliability of the reactor emergency shutdown system in an existing plant can be improved. It is possible to greatly improve the performance through inexpensive and simple construction.

(実施例) 本発明の実施例を図面を参照して説明する。(Example) Embodiments of the present invention will be described with reference to the drawings.

第1図は本発明の一実施例の概略構成図を示すものであ
り、既に説明した第2図の従来例と同一構成部分には同
一符号を付して説明する。
FIG. 1 shows a schematic configuration diagram of an embodiment of the present invention, and the same components as those of the conventional example shown in FIG. 2 already explained are given the same reference numerals and explained.

まず、制御棒の緊急挿入動作について説明する。First, the emergency insertion operation of the control rod will be explained.

水圧制御ユニット3のスクラム人口弁4およびスクラム
出目弁5は通常運転時には閉じているが、スクラム時に
はスクラム入口弁4が開き、アキュムレータ6から制御
棒駆動機構7のシリンダ部8に高圧の駆動水が送られる
とともにスクラム出口弁5が開き、制御棒駆動機構7の
シリンダ上部9の駆動水はスクラム排出容器10に排出
される。したがって、制御棒駆動機構7は下方から上方
に向かって原子炉内に挿入される。この水圧制御ユニッ
ト3および制御棒駆動機構7は、各制御棒毎に具備され
ている。
The scram population valve 4 and scram exit valve 5 of the water pressure control unit 3 are closed during normal operation, but during scram, the scram inlet valve 4 opens, and high-pressure drive water is supplied from the accumulator 6 to the cylinder section 8 of the control rod drive mechanism 7. At the same time, the scram outlet valve 5 opens, and the drive water in the cylinder upper part 9 of the control rod drive mechanism 7 is discharged into the scram discharge container 10. Therefore, the control rod drive mechanism 7 is inserted into the reactor from the bottom to the top. The hydraulic control unit 3 and control rod drive mechanism 7 are provided for each control rod.

次に、スクラム人口弁4およびスクラム出口弁5の開閉
制御について説明する。
Next, the opening/closing control of the scram population valve 4 and the scram outlet valve 5 will be explained.

スクラム人口弁4およびスクラム出口弁5は空気作動で
おり、空気圧が喪失すると開く設計となっている。常時
は計装用空気がスクラム・エア・ヘッダー11に供給さ
れ、この空気圧により前記スクラム人口弁4およびスク
ラム出口弁5の閉状態が維持されている。
The scram population valve 4 and the scram outlet valve 5 are pneumatically operated and are designed to open upon loss of air pressure. Instrument air is normally supplied to the scram air header 11, and this air pressure keeps the scram population valve 4 and the scram outlet valve 5 closed.

前記したようにスクラム信号S1が発生すると、各制御
棒に固有のスクラムパイロット弁12が計装用空気の供
給側を遮断するとともに、排気側を開くように動作し、
スクラム・エア・ヘッダー11内の空気が排気されるの
で、空気圧が喪失し、スクラム人口弁4およびスクラム
出目弁5が開き、制御棒駆動機構が動作し制御棒が緊急
挿入される。
As described above, when the scram signal S1 is generated, the scram pilot valve 12 specific to each control rod operates to shut off the instrument air supply side and open the exhaust side,
As the air in the scram air header 11 is exhausted, air pressure is lost, the scram population valve 4 and the scram exit valve 5 open, the control rod drive mechanism operates, and the control rod is emergency inserted.

ざらに、スクラムパイロット弁12とは独立に、全制御
棒に共通の後備緊急停止弁13が設けられており、この
後備緊急停止弁13もスクラム信号S1でスクラム・エ
ア・ヘッダー11の排気を行い、スクラム動作を行うこ
とができる。
Roughly speaking, a backup emergency stop valve 13 common to all control rods is provided independently of the scram pilot valve 12, and this backup emergency stop valve 13 also exhausts the scram air header 11 in response to the scram signal S1. , can perform Scrum operations.

以上説明した制御棒の緊急挿入動作及びスクラム人口弁
4およびスクラム出口弁5の開閉制御に関しては従来例
と同様である。本実施例では、従来の検出器1とは独立
した検出器14を設け、スクラムに失敗した場合の対処
が非常に厳しくなる原子炉圧力高、原子炉水位低のパラ
メータについての検出信号を、スクラム論理回路2と独
立した代替制御棒挿入論理回路15に入力し、スクラム
信号S1とは全く独立した代替制御棒挿入信号S2を生
成し、既存の後備緊急停止弁13を動作させて、スクラ
ム・エア・ヘッダー11の排気を行い、制御棒の緊急挿
入を行うように構成したものである。
The emergency insertion operation of the control rods and the opening/closing control of the scram artificial valve 4 and the scram outlet valve 5 described above are the same as in the conventional example. In this embodiment, a detector 14 independent from the conventional detector 1 is provided, and detection signals regarding parameters such as high reactor pressure and low reactor water level, which would be extremely difficult to deal with in the event of a scram failure, are transmitted to the scram. The signal is input to an alternative control rod insertion logic circuit 15 that is independent of the logic circuit 2, generates an alternative control rod insertion signal S2 that is completely independent of the scram signal S1, and operates the existing standby emergency stop valve 13 to prevent scram air.・It is configured to exhaust the header 11 and perform emergency insertion of control rods.

本実施例の場合、従来の原子炉緊急停止装置でも最も故
障に対する寄与が大きかったスクラム論理回路2および
検出器1が冗長化、多様化されるため、これらに起因す
る原子炉緊急停止装置の信頼性が大巾に向上する。さら
に、複雑で高価なスクラム・エア・ヘッダー11への代
替制御棒挿入弁の設置、改造工事が不要であるので、比
較的安価な論理回路や検出器の増設のみで既設プラント
に導入することが可能となる。
In the case of this embodiment, the scram logic circuit 2 and the detector 1, which contributed the most to failures in conventional reactor emergency shutdown systems, are made redundant and diversified, so the reliability of the reactor emergency shutdown system due to these is made redundant and diversified. Sexuality is greatly improved. Furthermore, since there is no need to install an alternative control rod insertion valve or modify the complicated and expensive scram air header 11, it can be introduced into an existing plant by simply adding relatively inexpensive logic circuits and detectors. It becomes possible.

また、本実施例では検出器14を既存の検出器1とは独
立に設けた場合について説明したが、この検出器14に
既存の検出器1を流用すると、より安価に既設プラント
の原子炉緊急停止装置の信頼性を向上されることが可能
になる。
In addition, in this embodiment, the case where the detector 14 is installed independently from the existing detector 1 has been explained, but if the existing detector 1 is used as this detector 14, it is possible to reduce the cost and reduce the risk of reactor emergency in an existing plant. It becomes possible to improve the reliability of the stopping device.

なお、検出器14は全てのスクラムパラメータに対して
設置する必要は必ずしもなく、上述したようにスクラム
に失敗した場合の対処が非常に厳しくなるパラメータに
ついてのみ設置すればよい。
Note that the detector 14 does not necessarily need to be installed for all the scrum parameters, and may be installed only for the parameters for which it is extremely difficult to deal with a scrum failure as described above.

[発明の効果] 以上説明してきたように、本発明によれば、万一、機能
喪失した場合にその影響を緩和することが非常に厳しい
原子炉緊急停止装置の信頼性を大巾に向上させることが
可能になり、より一層原子炉の安全性が向上する。ざら
に、新設プラントへの導入は勿論のこと、既設プラント
への導入も、比較的容易に行うことが可能となる。
[Effects of the Invention] As explained above, according to the present invention, the reliability of the nuclear reactor emergency shutdown system, in which it is extremely difficult to alleviate the effects in the event of loss of function, can be greatly improved. This makes it possible to further improve the safety of nuclear reactors. In general, it can be relatively easily introduced not only into new plants but also into existing plants.

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

第1図は本発明の一実施例の原子炉緊急停止装置の概略
構成図、第2図は従来の原子炉緊急停止装置の概略構成
図である。 1.14・・・検出器、    2・・・スクラム論理
回路3・・・水圧制御ユニット、4・・・スクラム人口
弁5・・・スクラム出口弁、 6・・・アキュムレータ
7・・・制御棒駆動機構、 8・・・シリンダ部9・・
・シリンダ上部、10・・・スクラム排出容器11・・
・スクラム・エア・ヘッダー 12・・・スクラムパイロット弁 13・・・後備緊急停止弁 15・・・代替制御棒挿入論理回路 16・・・代替制御棒挿入弁 (8733)代理人 弁理士 猪 股 祥 晃(ばか 
1名) 第1図
FIG. 1 is a schematic diagram of a nuclear reactor emergency shutdown system according to an embodiment of the present invention, and FIG. 2 is a schematic diagram of a conventional nuclear reactor emergency shutdown system. 1.14...Detector, 2...Scram logic circuit 3...Water pressure control unit, 4...Scram population valve 5...Scram outlet valve, 6...Accumulator 7...Control rod Drive mechanism, 8... cylinder part 9...
・Cylinder top, 10...Scrum discharge container 11...
・Scram air header 12...Scram pilot valve 13...Backup emergency stop valve 15...Alternative control rod insertion logic circuit 16...Alternative control rod insertion valve (8733) Agent Patent attorney Sho Inomata Akira (idiot)
1 person) Figure 1

Claims (1)

【特許請求の範囲】[Claims]  原子炉のパラメータを検出する検出器と、この検出器
から得られた検出信号に基づいて原子炉の緊急停止信号
を生成する論理回路と、前記緊急停止信号により各制御
棒に固有の排気弁および全制御棒に共通の後備緊急停止
弁を動作させ空気ヘッダーの空気を排気することにより
制御棒を緊急挿入して原子炉を緊急停止する原子炉緊急
停止装置において、前記検出器とは独立した検出器およ
び前記論理回路とは独立した論理回路を設け、この独立
した論理回路によっても前記後備緊急停止弁を動作させ
原子炉を緊急停止させるように構成したことを特徴とし
た原子炉緊急停止装置。
a detector for detecting reactor parameters; a logic circuit for generating an emergency stop signal for the reactor based on the detection signal obtained from the detector; In a reactor emergency shutdown system that operates a backup emergency stop valve common to all control rods and exhausts the air in the air header to urgently insert control rods and shut down the reactor, a detection system independent of the detector described above is used. A nuclear reactor emergency shutdown system, characterized in that a logic circuit is provided that is independent of the reactor and the logic circuit, and the independent logic circuit also operates the backup emergency stop valve to bring the reactor to an emergency shutdown.
JP1103373A 1989-04-25 1989-04-25 Reactor emergency stop device Expired - Fee Related JP2740000B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1103373A JP2740000B2 (en) 1989-04-25 1989-04-25 Reactor emergency stop device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1103373A JP2740000B2 (en) 1989-04-25 1989-04-25 Reactor emergency stop device

Publications (2)

Publication Number Publication Date
JPH03128488A true JPH03128488A (en) 1991-05-31
JP2740000B2 JP2740000B2 (en) 1998-04-15

Family

ID=14352304

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1103373A Expired - Fee Related JP2740000B2 (en) 1989-04-25 1989-04-25 Reactor emergency stop device

Country Status (1)

Country Link
JP (1) JP2740000B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2016063374A1 (en) * 2014-10-22 2016-04-28 三菱電機株式会社 Remote integrated monitoring operation system

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02181695A (en) * 1989-01-06 1990-07-16 Toshiba Corp Nuclear reactor protection device

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02181695A (en) * 1989-01-06 1990-07-16 Toshiba Corp Nuclear reactor protection device

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2016063374A1 (en) * 2014-10-22 2016-04-28 三菱電機株式会社 Remote integrated monitoring operation system
JPWO2016063374A1 (en) * 2014-10-22 2017-04-27 三菱電機株式会社 Remote integrated monitoring and operation system

Also Published As

Publication number Publication date
JP2740000B2 (en) 1998-04-15

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