JPS58120194A - Protection device for atomic power plant - Google Patents
Protection device for atomic power plantInfo
- Publication number
- JPS58120194A JPS58120194A JP57002881A JP288182A JPS58120194A JP S58120194 A JPS58120194 A JP S58120194A JP 57002881 A JP57002881 A JP 57002881A JP 288182 A JP288182 A JP 288182A JP S58120194 A JPS58120194 A JP S58120194A
- Authority
- JP
- Japan
- Prior art keywords
- protection device
- signal
- water level
- power plant
- flow rate
- 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
-
- 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
- Emergency Protection Circuit Devices (AREA)
- Protection Of Static Devices (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】
発明の技術分野
本発明は原子力発電所の保護装置に係り、特にプロセス
計算機の機能を有効に利用して原子カプラントの重要機
器の保護機能を向上させた原子力発電所の保護装置に関
する。DETAILED DESCRIPTION OF THE INVENTION Technical Field of the Invention The present invention relates to a protection device for a nuclear power plant, and in particular to a protection device for a nuclear power plant that effectively utilizes the functions of a process computer to improve the protection function of important equipment in an atomic couplant. Regarding protective devices.
発明の技術的背景
原子力発電所においては、原子炉、タービン、発電機そ
の他の重要機器の異常が発生した際、これを直ちに検知
し、重大事故に発展する前に機器を自動的に停止あるい
はインタロックするための保護装置が多数設けられてい
る。Technical background of the invention In nuclear power plants, when an abnormality occurs in the reactor, turbine, generator, or other important equipment, it is immediately detected and the equipment is automatically stopped or interfaced before it develops into a serious accident. A number of locking protection devices are provided.
これらの保護装置はプラントの安全性を維持する上で必
要不可欠のものであるが、保護装置自体が充分に高い信
頼性を有しないと、プラントの稼動率をいたずらに低下
させることになるので、従来から、保護装置の信頼性を
向上させるための種々の対策が講じられている。These protective devices are essential for maintaining plant safety, but if the protective devices themselves are not sufficiently reliable, they will unnecessarily reduce the plant's operating rate. Conventionally, various measures have been taken to improve the reliability of protection devices.
即ち、例えば単一の信号で保護装置を動作させるように
しておくと、信号自体に誤りがあった場合にも保護装置
が動作するので、これを避ける姶め、同一の信号を複数
個(通常は3〜4個)の計側蓋によって検出し、それら
の一致信号で保護装置を動作させるようにしている。In other words, for example, if a single signal is used to activate a protection device, the protection device will be activated even if there is an error in the signal itself. is detected by three or four side covers, and the protection device is activated by the matching signals.
背景技術の問題点
上述の、同一信号を複数個の計測器によって検出する方
式は計測器の設置個数が増大し、機器の保守を難かしく
する上、プラントのコストを上昇させるという不都合が
ある。Problems with the Background Art The method described above in which the same signal is detected by a plurality of measuring instruments has the disadvantage that the number of installed measuring instruments increases, which makes maintenance of the equipment difficult and increases the cost of the plant.
発明の目的
本発明は従来の保護装置における上述の如き不都合を除
去すべくなされたもので、原子カプラントに標準的に設
置されているプロセス計算機の出力信号を有効に利用す
ることによって、計測器の設置個数の増加を伴なうこと
なく、保護機能の信頼性を向上させた原子力発電所の保
護装置を提供することを目的とするものである。Purpose of the Invention The present invention has been made to eliminate the above-mentioned disadvantages in conventional protection devices, and by effectively utilizing the output signal of the process computer installed as standard in the atomic coupler, The object of the present invention is to provide a protection device for a nuclear power plant that improves the reliability of the protection function without increasing the number of devices installed.
発明の概要
本発明は、上述の目的を達成するため、原子カプラント
の重要機器の状態を検出する計測器を、同一信号につき
1個のみ使用し、この計測器の出力信号と、この出力信
号に対して相関性を有するプロセス計算機の出力信号と
の一致信号によって保護動作を行なうよう構成した原子
力発電所の保護装置である。SUMMARY OF THE INVENTION In order to achieve the above-mentioned object, the present invention uses only one measuring device for the same signal to detect the status of important equipment of an atomic couplant, and uses the output signal of this measuring device and the output signal of this measuring device. This is a protection device for a nuclear power plant configured to perform a protection operation based on a signal that matches the output signal of a process computer that has a correlation with the output signal of a process computer.
発明の実施例
以下、図面に示す本発明の実施例につき、その詳細を説
明する。Embodiments of the Invention Hereinafter, embodiments of the invention shown in the drawings will be explained in detail.
図は原子カプラントにおいて、原子炉の炉内水位が異常
に上昇した際にタービンの自動停止動作を行なう保護装
置を例示するものである。The figure illustrates a protection device that automatically shuts down a turbine when the water level inside a nuclear reactor rises abnormally in a nuclear reactor.
原子炉1で発生した蒸気は主蒸気管2を通してタービン
乙に導かれ、ここで仕事をした後、図示を省略した復水
器(二よって復水となり、給水ポンプ4で加圧され、給
水管5を通して再び原子炉1内に導入される。The steam generated in the reactor 1 is led to the turbine 2 through the main steam pipe 2, and after doing work there, it becomes condensed water, which is pressurized by the water supply pump 4, and then transferred to the water supply pipe. 5 into the reactor 1 again.
主蒸気管2に取付けた主蒸気流量検出器6および給水管
5に取付けた給水流量検出器7がらの流量信号は、原子
炉1、タービン3、発電機等の重要機器に取付けた、そ
の他の各種や計測器(図示せず)からの信号と共に、プ
ロセス計算機8にインプットされている。The flow rate signals from the main steam flow rate detector 6 attached to the main steam pipe 2 and the feed water flow rate detector 7 attached to the water supply pipe 5 are transmitted to other important equipment attached to the reactor 1, turbine 3, generator, etc. It is input to the process computer 8 along with signals from various instruments and measuring instruments (not shown).
3−
このプロセス計算機は各種多数の計測器からの入力信号
を常時、オンラインでスキャンニングし、各種の性能計
算やプラント状態の変化を監視している。3- This process computer constantly scans input signals from a large number of various measuring instruments online, and monitors various performance calculations and changes in plant status.
原子炉1内の水位は1チヤンネルの原子炉水位検出器9
によって検出され、その出力はタービン保護装置10に
インプットされる。The water level inside the reactor 1 is measured by a 1-channel reactor water level detector 9.
and its output is input to the turbine protection device 10.
一方、プロセス計算機8では、主蒸気流量検出器6と給
水流量検出器7からの信号に基いて、主蒸気流量と給水
流量との差を常に比較チェックしており、両者の差が所
定の値を越えると、タービン保護装置10に向けて信号
を出力する。On the other hand, the process computer 8 constantly compares and checks the difference between the main steam flow rate and the feed water flow rate based on the signals from the main steam flow rate detector 6 and the feed water flow rate detector 7, and the difference between the two is determined to be a predetermined value. When the value exceeds 100, a signal is output to the turbine protection device 10.
タービン保護装置10はプロセス計算機8からの信号と
、水位検出器9からの信号とが一致することを条件とし
て、タービン6に向けてタービン停止信号を出力し、タ
ービン6を停止させる。The turbine protection device 10 outputs a turbine stop signal to the turbine 6 to stop the turbine 6 on the condition that the signal from the process computer 8 and the signal from the water level detector 9 match.
上記において、原子炉の水位上昇は給水流量と主蒸気流
量との差に対して相関性を有しており、両流量がバラン
スしておれば水位変化は生じない訳であるから、プロセ
ス計算機から流量差の異常−4=
を示す信号が出力されていないにも拘らず、水位検出器
から、水位の異常上昇を示す信号が出力されている場合
には、水位検出器あるいはその伝送系統の誤信号を拾っ
ているものと判断される。In the above, the water level rise in the reactor is correlated with the difference between the feed water flow rate and the main steam flow rate, and if both flow rates are balanced, no water level change will occur. If the water level detector outputs a signal indicating an abnormal rise in the water level even though the signal indicating the abnormal flow rate difference -4= is not output, there is an error in the water level detector or its transmission system. It is assumed that the signal is being picked up.
このような場合、本発明の保護装置では、プロセス計算
機の出力と水位検出器からの出力がアンド条件を満足す
る場合に限って、タービン保護装置からタービン停止信
号を発信するようにしているので、保護機能の信頼性が
向上しており、タービンが必要以上にトリップされて、
プラントの稼動率が低下することを防止することができ
る。In such a case, in the protection device of the present invention, the turbine protection device sends a turbine stop signal only when the output from the process computer and the output from the water level detector satisfy the AND condition. The protection is more reliable and the turbine is not tripped more than necessary.
It is possible to prevent the operating rate of the plant from decreasing.
なお、上述の例においては、プロセス計算機の入力信号
である給水流量と主蒸気流量は、原子炉の炉心性能計算
のため従来から入力されているものであるから、本発明
を適用する際に新たな計測器を追加する必要はなく、単
にプロセス計算機内に給水流量と主蒸気流量とを比較判
定するためのロジックを追加するだけでよい1、
以上の説明では、原子炉水位が異常に上昇した場合にタ
ービンを自動停止させる場合を例にとって述べたが、本
発明は原子炉水位が規定値以下に低下した際に原子炉を
自動停止させる場合にも上記と同様に適用することがで
き、更には、従来からプロセス計算機に入力されている
信号で、別置の計測器の出力信号と相関関係のある信号
であれば上記と同様にして保護回路を組むことができる
。In the above example, the feed water flow rate and main steam flow rate, which are the input signals of the process computer, are conventionally input for calculating the reactor core performance, so new input signals are required when applying the present invention. There is no need to add any additional measuring equipment, just add logic to compare and judge the feed water flow rate and main steam flow rate in the process computer1. In the above explanation, the reactor water level has risen abnormally. Although the present invention has been described using an example in which the turbine is automatically stopped when the reactor water level falls below a specified value, the present invention can be applied in the same manner as above to the case where the reactor is automatically stopped when the reactor water level falls below a specified value. is a signal that has been conventionally input to a process computer, and if it is a signal that has a correlation with the output signal of a separate measuring instrument, a protection circuit can be built in the same manner as described above.
発明の効果
上述の如く、本発明は原子力発電所に標準的に設置され
ているプロセス計算機を利用することによって剖側蓋の
チャンネル数を増加させることなしに保護装置の信頼性
を向上させることができるので、1つの機能を遂行する
ために複数の装置を併設する従来の多重化方式に比較し
てスペース上の制約や保守部品の増加、コストの上昇と
いった問題を解消でき、経済性が高く、プラントの稼動
率の向上に寄与し得る保護装置が得られる。Effects of the Invention As described above, the present invention makes it possible to improve the reliability of the protection device without increasing the number of channels in the autopsy side cover by utilizing the process computer that is installed as standard in nuclear power plants. Compared to the conventional multiplexing method in which multiple devices are installed together to perform a single function, it is highly economical and eliminates problems such as space constraints, increased number of maintenance parts, and increased costs. A protection device that can contribute to improving the operating rate of a plant can be obtained.
図は本発明を、原子炉の水位上昇に際してタービンを自
動停止させるタービン保護装置に適用した例を示す系統
図である。
1 ・・・・・・ 原子炉
2 ・・・・・・ 主蒸気管
6 ・・・・・・ タービン
4 ・・・・・・ 給水ポンプ
5 ・・・・・・給水管
6 ・・・・・・主蒸気流量検出器
7 ・・・・・・給水流量検出器
8 ・・・・・・ プロセス計算機
9 ・・・・・・水位検出器
10 ・・・・・・ タービン保護装置(7317)代
理人弁理士 則 近 憲 佑(ほか1名)The figure is a system diagram showing an example in which the present invention is applied to a turbine protection device that automatically stops a turbine when the water level of a nuclear reactor rises. 1 ..... Reactor 2 ..... Main steam pipe 6 ..... Turbine 4 ..... Water pump 5 ..... Water supply pipe 6 .... ...Main steam flow rate detector 7 ...Feed water flow rate detector 8 ...Process computer 9 ...Water level detector 10 ...Turbine protection device (7317) Representative Patent Attorney Noriyuki Chika (and 1 other person)
Claims (1)
を同一信号につき1個のみ使用し、この計測器の出力信
号と、この出力信号に対して相関性を有するプロセス計
算機の出力信号との一致信号によって保護動作を行なう
よう構成したことを特徴とする原子力発電所の保護装置
。 2、計測器が原子炉水位の異常上昇によって出力を生ず
る水位検出器であり、プロセス計算機の出力信号が主蒸
気流量と給水流量の差を示す信号であり、前記水位検出
器の出力信号と前記プロセス計算機の出力信号が一致し
た際、タービンに停止信号を送出するよう構成したこと
を特徴とする特許請求の範囲第1項記載の原子力発電所
の保護装置。[Claims] 1. A process computer that uses only one measuring device for each signal to detect the status of important equipment in an atomic couplant, and has a correlation between the output signal of this measuring device and this output signal. A protection device for a nuclear power plant, characterized in that the protection device is configured to perform a protection operation based on a signal that matches an output signal of the device. 2. The measuring device is a water level detector that generates an output due to an abnormal rise in the reactor water level, and the output signal of the process computer is a signal indicating the difference between the main steam flow rate and the feed water flow rate, and the output signal of the water level detector and the The protection device for a nuclear power plant according to claim 1, wherein the protection device for a nuclear power plant is configured to send a stop signal to the turbine when the output signals of the process computer match.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57002881A JPS58120194A (en) | 1982-01-13 | 1982-01-13 | Protection device for atomic power plant |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57002881A JPS58120194A (en) | 1982-01-13 | 1982-01-13 | Protection device for atomic power plant |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS58120194A true JPS58120194A (en) | 1983-07-16 |
Family
ID=11541693
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP57002881A Pending JPS58120194A (en) | 1982-01-13 | 1982-01-13 | Protection device for atomic power plant |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS58120194A (en) |
-
1982
- 1982-01-13 JP JP57002881A patent/JPS58120194A/en active Pending
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