JPS59131199A - Device for detecting abnormality in main steam circuit of bwr type reactor - Google Patents
Device for detecting abnormality in main steam circuit of bwr type reactorInfo
- Publication number
- JPS59131199A JPS59131199A JP58005486A JP548683A JPS59131199A JP S59131199 A JPS59131199 A JP S59131199A JP 58005486 A JP58005486 A JP 58005486A JP 548683 A JP548683 A JP 548683A JP S59131199 A JPS59131199 A JP S59131199A
- Authority
- JP
- Japan
- Prior art keywords
- main steam
- abnormality
- flow rate
- steam
- steam flow
- 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
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
- Monitoring And Testing Of Nuclear Reactors (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〕
本発明は沸騰水型原子炉(BWR)の主蒸気系異常検知
装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a main steam system abnormality detection device for a boiling water reactor (BWR).
BWRO主蒸気系は第1図に示すように構成されている
。すなわち、原子炉1と、原子炉格納容器の壁体2を貫
通し容器外に設けた主蒸気ヘッダ3に、原子炉1から蒸
気を導く4本の主蒸気管48〜4dと、主蒸気へラダ3
から各タービン(図示しない)に蒸気を導く配管5a〜
5dと、各主蒸気配管4a〜4dの最上流側に設けた蒸
気流量検出器6a〜6dと、各主蒸気配管4a〜4dの
壁体2上流側、下流側に設けた第1主蒸気隔離弁78〜
7d、第2主蒸気隔離弁88〜8dとにより構成されて
いる。The BWRO main steam system is constructed as shown in FIG. That is, four main steam pipes 48 to 4d that lead steam from the reactor 1 to a main steam header 3 that penetrates the reactor 1 and the wall 2 of the reactor containment vessel and are provided outside the vessel, and four main steam pipes 48 to 4d that lead steam from the reactor 1 to the main steam Lada 3
Piping 5a to guide steam from the turbine to each turbine (not shown)
5d, steam flow rate detectors 6a to 6d provided on the most upstream side of each main steam piping 4a to 4d, and first main steam isolation devices provided on the upstream and downstream sides of wall 2 of each main steam piping 4a to 4d. Valve 78~
7d, and second main steam isolation valves 88 to 8d.
上記の構成において、第1、第2の主蒸気隔離弁7a〜
7d、8a〜8dは、主蒸気管漏洩などの事故発生時に
閉塞させ、原子炉1内の冷却材、放射性物質の格納容器
外への放出を制限するものである。また、蒸気流量検出
器6a〜6dの出力は、原子炉1内の水位を一定に保持
する原子炉給水制御系で、制御入力の一つとして使用さ
れる。In the above configuration, the first and second main steam isolation valves 7a to
7d and 8a to 8d are closed in the event of an accident such as a leakage of the main steam pipe, thereby restricting the release of coolant and radioactive materials inside the reactor 1 to the outside of the containment vessel. Further, the outputs of the steam flow rate detectors 6a to 6d are used as one of the control inputs in a reactor feed water control system that maintains the water level in the reactor 1 constant.
蒸気流量検出器6a〜6dが故障して、その出力信号が
実際より大きくなれば主蒸気流量を過大評価することと
なり、実際より小さくなれば過小評価することとなる。If the steam flow rate detectors 6a to 6d fail and their output signals become larger than the actual one, the main steam flow rate will be overestimated, and if it becomes smaller than the actual one, the main steam flow rate will be underestimated.
従って、蒸気流量検出器6a〜6dが故障すれば、原子
炉給水制御系は原子炉水位を一定に保持することができ
なくなる。そのため、蒸気流量検出器6a〜6dが故障
した場合には、それをBWR運転員に速やかに知らせ、
適切な処置をとらせなければならない。Therefore, if the steam flow rate detectors 6a to 6d fail, the reactor feed water control system will not be able to maintain the reactor water level constant. Therefore, if the steam flow rate detectors 6a to 6d are out of order, the BWR operator will be notified immediately.
Appropriate measures must be taken.
また、BWR中央制御室の制御盤には、第1、第2の主
蒸気隔離弁7a〜7d、8a〜8dの開閉状態を示すラ
ンプが設けてあり、BWR運転員はそれにより各主蒸気
隔離弁の開閉状態を知ることができる。ところが、蒸気
流量検出器6a〜6dの出力信号すなわち蒸気流量信号
が小さくなった場合でも、前記のランプが故障していた
り、各主蒸気隔離弁の開閉信号自体に異常があったりす
れば、蒸気流量信号が小さくなった原因が、主蒸気隔離
弁の閉鎖にあるのか、蒸気流量検出器の故障にあるのか
を判別することはできない。そのため、BWR運転員は
速やかに適切な処置をとり得す、原子炉トリップにいた
ることがある。なお、上記とは逆に主蒸気隔離弁閉の表
示であるにもかかわらず、蒸気流量信号がある値を保っ
ている場合も同様にして原子炉トリップにいたることも
ある。In addition, the control panel of the BWR central control room is equipped with lamps that indicate the open/closed status of the first and second main steam isolation valves 7a to 7d, and 8a to 8d. You can know whether the valve is open or closed. However, even if the output signal of the steam flow rate detectors 6a to 6d, that is, the steam flow rate signal, becomes small, if the lamp is malfunctioning or there is an abnormality in the opening/closing signal of each main steam isolation valve, the steam It is not possible to determine whether the low flow signal is due to the closure of the main steam isolation valve or a failure of the steam flow detector. This may result in a reactor trip, for which BWR operators can take appropriate action immediately. Note that, contrary to the above, even if the steam flow rate signal maintains a certain value despite the indication that the main steam isolation valve is closed, a reactor trip may occur in the same way.
本発明は上記の事情に基きなされたもので、主蒸気隔離
弁閉信号が出ていないにもかかわらず、蒸気流量信号の
値が小さくなっh時や、逆に閉信号になっているにもか
かわらず蒸気流量信号がある値を保持している時に、そ
の異常原因と異常箇所を検知することができるBWR主
蒸気系異常検知装置を得ることを目的としている。The present invention has been made based on the above-mentioned circumstances, and even when the value of the steam flow rate signal becomes small even though the main steam isolation valve close signal is not output, or conversely, even when the close signal is displayed. The object of the present invention is to obtain a BWR main steam system abnormality detection device that can detect the cause and location of an abnormality when a steam flow rate signal maintains a certain value regardless of the situation.
本発明においては、各主蒸気管に設けた蒸気流量検出器
の蒸気流量信号を入力するアナログ信号入力部と、各主
蒸気管の主蒸気隔離弁の弁開閉信号を入力するデジタル
信号入力部と、それらの入力信号と自ら診断した結果の
主蒸気管異常フラグとをもとに求めた平均蒸気流量と各
主蒸気管の蒸気流量との差の絶対値の最大のものが予め
定めた正の小さな値より大きい場合に主蒸気系に異常が
発生したと見なしその発生個所および異常原因を診断す
る異常診断部と、診断結果を表示する表示部とを有する
ことにより沸騰水型原子炉の主蒸気系異常検知装置を構
成して前記目的を達成している。The present invention includes an analog signal input section that inputs the steam flow rate signal of the steam flow rate detector provided in each main steam pipe, and a digital signal input section that inputs the valve opening/closing signal of the main steam isolation valve of each main steam pipe. , the maximum absolute value of the difference between the average steam flow rate calculated based on these input signals and the main steam pipe abnormality flag as a result of self-diagnosis and the steam flow rate of each main steam pipe is determined by a predetermined positive value. If the value is larger than a small value, it is assumed that an abnormality has occurred in the main steam system, and the system has an abnormality diagnosis section that diagnoses the location and cause of the abnormality, and a display section that displays the diagnosis results. The above objective is achieved by configuring a system abnormality detection device.
第1図と同一部分には同一符号を附した第2図は本発明
の一実施例を示し、この図において主蒸気系異常検知装
置9は、蒸気流量検出器6a〜6dの蒸気流量信号を入
力されるアナログ信号入力部10と、第1、第2の主蒸
気隔離弁7a〜7d。FIG. 2, in which the same parts as in FIG. 1 are given the same reference numerals, shows an embodiment of the present invention. An input analog signal input section 10 and first and second main steam isolation valves 7a to 7d.
8a〜8dの開閉信号が入力されるデジタル信号入力部
11とを有する。蒸気流量信号は、アナログ信号入力部
10において、蒸気流量m19m2.WL3゜第4(t
/hr)に変換される。また、主蒸気隔離弁開閉信号は
、デジタル信号入力部において、主蒸気隔離弁閉鎖フラ
グg1. g2. ga、 g4に変換される。ここで
、gI(i=1〜4)は第1番目の主蒸気管に設けた2
箇の主蒸気隔離弁の中少くとも1箇が閉信号であれば、
gI−〇、その他はg1=1とする。It has a digital signal input section 11 into which opening/closing signals 8a to 8d are input. The steam flow rate signal is input to the analog signal input section 10 as steam flow rate m19m2. WL3゜4th (t
/hr). Furthermore, the main steam isolation valve opening/closing signal is input to the main steam isolation valve closing flag g1. g2. ga, converted to g4. Here, gI (i = 1 to 4) is the second main steam pipe installed in the first main steam pipe.
If at least one of the main steam isolation valves has a close signal,
gI-〇, otherwise g1=1.
入力結果であるm+ gtは異常診断部12に入力さ
れ、診断結果はCRTまたはランプ等で構成された異常
表示部13に表示される。The input result m+gt is input to the abnormality diagnosis section 12, and the diagnosis result is displayed on the abnormality display section 13 composed of a CRT, a lamp, or the like.
異常診断部はマイクロコンピュータ等により構成され、
次のようにして診断を行う。すなわち、異常診断部12
内にはフラグ処理部14、平均蒸気流量計算部15、異
常検知部16、偏差符号判別部17、第1異常個所検索
部18、第2異常検索部19が設けて゛あり、フラグ処
理部14では異常個所検索部18.19で主蒸気管に何
らかの異常があれば0、正常であれば1とセットされる
主蒸気管異常フラグf、と、主蒸気隔離弁閉鎖フラグg
。The abnormality diagnosis section is composed of a microcomputer, etc.
Diagnosis is performed as follows. That is, the abnormality diagnosis section 12
A flag processing unit 14, an average steam flow rate calculation unit 15, an abnormality detection unit 16, a deviation sign determination unit 17, a first abnormality location search unit 18, and a second abnormality search unit 19 are provided within the flag processing unit 14. The abnormality location search unit 18.19 sets a main steam pipe abnormality flag f, which is set to 0 if there is any abnormality in the main steam pipe, and 1 if it is normal, and a main steam isolation valve closing flag g.
.
との積の総和Tが計算される。次に、平均蒸気流量計算
部15では、下式(1)、(2)から平均圧損係数KA
Vと平均蒸気流量771AVを求める。ただし、総和T
がOの場合にはmAVを強制的に0とおく。The sum T of the products is calculated. Next, the average steam flow rate calculation unit 15 calculates the average pressure loss coefficient KA from the following equations (1) and (2).
Find V and the average steam flow rate of 771 AV. However, the total T
When is O, mAV is forcibly set to 0.
mAV−’Σ・右” g t r −mt ”’ (2
)T−JT’に’: ’
」二式中、K、は第1番目の主蒸気管の圧損係数であり
、ベルヌーイの法則から原子炉1とへラダ3との差圧△
Pが下式(8)となるよう、各主蒸気管4a〜4dにつ
き詳細計算か実測によって求めておく。mAV-'Σ・Right"g tr-mt"' (2
) T-JT': ' In the two equations, K is the pressure drop coefficient of the first main steam pipe, and from Bernoulli's law, the differential pressure between reactor 1 and Herada 3 is △
P is determined by detailed calculation or actual measurement for each main steam pipe 4a to 4d so that it satisfies the following formula (8).
△P=に+m+ ・・・・・・・・・・・・・・・・
・・・・・・・・・・・・・・(8)異常検知部16は
、下式(4)で与えられろ偏差砺の絶対値最大のものを
捜し、それをE、とじこのEjと予め定めた正の小さい
数εとを比較する。E。△P=to+m+ ・・・・・・・・・・・・・・・・
(8) The abnormality detection unit 16 searches for the maximum absolute value of the deviation coefficient given by the following formula (4), and sets it as E and the binding Ej. and a predetermined small positive number ε. E.
がεより小であれば、新たな異常の発生はな〜・ものと
して、診断を終了する。E、がεよりも大きければ、偏
差符号判別部17以降におし・て異常発生の原因をさぐ
ることとなる。If is smaller than ε, it is assumed that no new abnormality has occurred, and the diagnosis is terminated. If E is larger than ε, the cause of the abnormality is investigated in the deviation sign determining section 17 and thereafter.
E+ =f + (Kmlgtびπ・m〜)・・・・
・・・・・・・・(4)すなわち、偏差符号判別部17
では、E、fJ−圧力・負かを判定し、正であれば第2
異常個所検索部19に移行する。負であれば、第1異常
個所検索部18で第j番目の主蒸気管の主蒸気隔離弁が
閉鎖、つまりgj”Oとして、下式(5)〜(ア)によ
り平均蒸気流量”’AVを計算し直す。E+ =f + (Kmlgt π・m~)...
(4) That is, the deviation sign determination unit 17
Then, determine E, fJ-pressure/negative, and if positive, the second
The process moves to the abnormal location search section 19. If it is negative, the first abnormality location search unit 18 determines that the main steam isolation valve of the j-th main steam pipe is closed, that is, as gj"O, the average steam flow rate "'AV Recalculate.
T=Σft g+ ・・・・・・・・・・・・・・・
・・・・・・・・・(5)その後、l mAV −’
AY Iがある正の小さな数ηより小であれば、第j番
目の主蒸気管の主蒸気隔離弁が閉じているにもかかわら
ず、弁閉信号が出ていない旨を、ηより大きければ第j
番目の主蒸気管の蒸気流量検出器が故障しており、その
出力信号が異常に低い旨をそれぞれ異常表示部13に表
示して、BWR運転員に知らせると共に、主蒸気管異常
フラグfj=0とする。T=Σft g+ ・・・・・・・・・・・・・・・
・・・・・・・・・(5) After that, l mAV −'
If AY I is smaller than a certain positive small number η, it means that the main steam isolation valve of the j-th main steam pipe is closed, but the valve close signal is not output; if it is larger than η, jth
The steam flow rate detector of the th main steam pipe is malfunctioning and its output signal is abnormally low, and this is displayed on the abnormality display section 13 to notify the BWR operator, and the main steam pipe abnormality flag fj = 0 shall be.
次に、第2異常個所検索部19では、BWR発電所に設
けられている蒸気漏洩検出系からの信号により、蒸気漏
洩の有無を検出し、蒸気漏洩が有ればその旨を表示部1
3に表示させ、同時に主蒸気管異常フラグf、=0とす
る。蒸気漏洩が無ければ、第1異常個所検索部18の場
合とは逆に、第j番目の主蒸気管に設けた主蒸気隔離弁
が開いている、つまりg」−1と仮定して式(5)〜(
7)から平均蒸気流量mχVを計算しなおし、l mA
V ”AV l < ’7であれば・第j番目の主蒸
気管の主蒸気隔離弁が全て開いているにもかかわらず、
弁閉信号が出ている旨を、また、l mvAm’hv
l 〉ηであれば、第j番目の主蒸気管の蒸気流量検出
器が故障し、その出力が異常に高い旨をそれぞれ表示部
13に表示させる。それと同時に主蒸気異常フラグf、
−〇とする。Next, the second abnormality location search unit 19 detects the presence or absence of steam leakage based on the signal from the steam leakage detection system installed in the BWR power plant, and if there is steam leakage, it displays this on the display unit 19.
3, and at the same time set the main steam pipe abnormality flag f,=0. If there is no steam leak, contrary to the case of the first abnormality location search unit 18, assuming that the main steam isolation valve provided in the j-th main steam pipe is open, that is, g'-1, the formula ( 5)~(
Recalculate the average steam flow rate mχV from 7) and obtain l mA
If V "AV l <'7, even though all the main steam isolation valves of the j-th main steam pipe are open,
In addition, l mvAm'hv indicates that the valve close signal is being output.
If l > η, the steam flow rate detector of the j-th main steam pipe has failed, and the display section 13 displays the fact that its output is abnormally high. At the same time, the main steam abnormality flag f,
−〇.
異常診断部には上記の診断を周期的に行う。The abnormality diagnosis section periodically performs the above diagnosis.
本発明によれば、BWRの主蒸気系に異常が発生し、各
主蒸気管の蒸気流量検出器が故障した場合に、その故障
した検出器および出力の増減を知ることかできる。また
、主蒸気隔離弁が開いているにもかかわらず弁閉鎖信号
が出ている場合、逆に閉じているのに弁閉鎖信号が出て
いない場合にも、それを知ることができる。よって、B
WR運転員はそれに対する処置を速やかにとることがで
き、原子炉トリップを防止することができる。According to the present invention, when an abnormality occurs in the main steam system of a BWR and the steam flow rate detector of each main steam pipe malfunctions, it is possible to know the malfunctioning detector and the increase/decrease in output. It is also possible to know if the main steam isolation valve is open but the valve close signal is being output, or conversely if the main steam isolation valve is closed but the valve close signal is not being output. Therefore, B
The WR operator can promptly take action to prevent a reactor trip.
第1図は従来のBWR主蒸気系の模式図、第2図は本発
明一実施例の模式図、第3図はその要部のブロック線図
である。
1・・・原子炉、 2・・・壁 体、3・・・
ヘッダ、 4a〜4d・・・主蒸気管、6a〜6d・
・・蒸気流量検出器、
7a〜7d、 8a〜8d・・・主蒸気隔離弁、10・
・・アナログ信号入力部、
11・・・デジタル信号入力部、12・・・異常診断部
、13・・・表示部
出願代理人 弁理士 菊 池 五 部FIG. 1 is a schematic diagram of a conventional BWR main steam system, FIG. 2 is a schematic diagram of an embodiment of the present invention, and FIG. 3 is a block diagram of the main parts thereof. 1... Nuclear reactor, 2... Wall body, 3...
Header, 4a-4d...Main steam pipe, 6a-6d...
...Steam flow rate detector, 7a-7d, 8a-8d...Main steam isolation valve, 10.
...Analog signal input section, 11...Digital signal input section, 12...Anomaly diagnosis section, 13...Display section Application agent Patent attorney Kikuchi Gobu
Claims (1)
力するアナログ信号入力部と、各主蒸気管の主蒸気隔離
弁の弁開閉信号を入力するデジタル信号入力部と、それ
らの入力信号と自ら診断した結果の主蒸気管異常フラグ
とをもとに求めた平均蒸気流量と各主蒸気管の蒸気流量
との差の絶対値の最大のものが予め定めた正の小さな値
より大きい場合に主蒸気不便異常が発生したと見なしそ
の発生個所および異常原因を診断する異常診断部と、診
断結果を表示する表示部とを有することを特徴とする沸
騰水型原子炉の主蒸気系異常検知装置。An analog signal input section that inputs the steam flow rate signal of the steam flow rate detector installed in each main steam pipe, a digital signal input section that inputs the valve opening/closing signal of the main steam isolation valve of each main steam pipe, and these input signals. If the maximum absolute value of the difference between the average steam flow rate calculated based on the main steam pipe abnormality flag as a result of self-diagnosis and the steam flow rate of each main steam pipe is larger than a predetermined small positive value. Main steam system abnormality detection for a boiling water reactor, characterized in that it has an abnormality diagnosis section that assumes that a main steam inconvenience abnormality has occurred and diagnoses the location and cause of the abnormality, and a display section that displays the diagnosis result. Device.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58005486A JPS59131199A (en) | 1983-01-17 | 1983-01-17 | Device for detecting abnormality in main steam circuit of bwr type reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58005486A JPS59131199A (en) | 1983-01-17 | 1983-01-17 | Device for detecting abnormality in main steam circuit of bwr type reactor |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS59131199A true JPS59131199A (en) | 1984-07-27 |
JPH051438B2 JPH051438B2 (en) | 1993-01-08 |
Family
ID=11612568
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP58005486A Granted JPS59131199A (en) | 1983-01-17 | 1983-01-17 | Device for detecting abnormality in main steam circuit of bwr type reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS59131199A (en) |
-
1983
- 1983-01-17 JP JP58005486A patent/JPS59131199A/en active Granted
Also Published As
Publication number | Publication date |
---|---|
JPH051438B2 (en) | 1993-01-08 |
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