JPS63109396A - Monitor for output distribution of nuclear reactor - Google Patents
Monitor for output distribution of nuclear reactorInfo
- Publication number
- JPS63109396A JPS63109396A JP61255393A JP25539386A JPS63109396A JP S63109396 A JPS63109396 A JP S63109396A JP 61255393 A JP61255393 A JP 61255393A JP 25539386 A JP25539386 A JP 25539386A JP S63109396 A JPS63109396 A JP S63109396A
- Authority
- JP
- Japan
- Prior art keywords
- neutron flux
- flux measuring
- power distribution
- measuring device
- 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.)
- Pending
Links
- 230000004907 flux Effects 0.000 claims description 60
- 238000012806 monitoring device Methods 0.000 claims description 9
- 238000000034 method Methods 0.000 claims description 4
- 238000005259 measurement Methods 0.000 claims description 3
- 238000004364 calculation method Methods 0.000 description 15
- 238000001514 detection method Methods 0.000 description 4
- 230000002159 abnormal effect Effects 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- 230000007257 malfunction Effects 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000012544 monitoring process Methods 0.000 description 2
- 241000981595 Zoysia japonica Species 0.000 description 1
- 230000005856 abnormality Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000004886 process control Methods 0.000 description 1
- 230000035945 sensitivity Effects 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
［発明の目的］
（産業上の利用分野）
本発明は、原子炉の出力分布を算出し監視する原子炉出
力分布監視装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a nuclear reactor power distribution monitoring device that calculates and monitors the power distribution of a nuclear reactor.
（従来の技術）
通常、原子炉には炉心内の出力分布の監視を行う目的で
プロセス制御計算機のような出方分布計算装置が付設さ
れている。この出方分布計算装置は、例えば沸騰水型原
子炉では炉心内に１００個以上配置された固定型中性子
束測定器の計数値に基づいて炉心内の出力分布を計算し
、これによって燃料の健全性ならびに炉心性能の評価が
行われている。(Prior Art) Normally, a nuclear reactor is equipped with an output distribution calculation device such as a process control computer for the purpose of monitoring the power distribution within the reactor core. For example, in a boiling water reactor, this output distribution calculation device calculates the power distribution within the reactor core based on the counts of more than 100 fixed neutron flux measuring devices placed in the reactor core. The performance and core performance are being evaluated.
このような固定型中性子束測定器は、第２図および第３
図に符号１で示すように、炉心を構成する燃料集合体２
間のギャップ３に設けられた導管４内に複数個具なる炉
心高さに配置されている。Such fixed neutron flux measuring instruments are shown in Figures 2 and 3.
As shown by reference numeral 1 in the figure, fuel assemblies 2 constituting the core
A plurality of them are arranged at different core heights in conduits 4 provided in gaps 3 between them.
また、この導管４は炉心内に数十個配置されており、そ
の全てに上記固定型中性子束測定器１が配置されている
。さらに、通常原子炉には複数の可動型中性子束測定器
５が備えられており、この可動型中性子束測定器５は固
定型中性子束測定器１が配置されている導管４内を動く
ことができ、固定型中性子束測定器１の較正に使用され
る。なお、両図において符号６は制御棒を示している。Moreover, several dozen of these conduits 4 are arranged in the reactor core, and the fixed neutron flux measuring device 1 is arranged in all of them. Furthermore, a nuclear reactor is usually equipped with a plurality of movable neutron flux measuring devices 5, and the movable neutron flux measuring devices 5 can move within the conduit 4 in which the fixed neutron flux measuring device 1 is arranged. It is used for calibrating the fixed neutron flux measuring instrument 1. In both figures, the reference numeral 6 indicates a control rod.
出力分布計算装置は上記の中性子束測定器の計数値を用
いて以下のように炉心の出力分布を計算する。The power distribution calculation device calculates the power distribution of the core as follows using the counts of the neutron flux measuring device described above.
Ｐ（Ｌ、Ｊ、に）＝ＥＲ（Ｌ、Ｋ）・ｇ（Ｌ、Ｊ、Ｋ）
・・・・・・・・・（Ｉ）
ここで、Ｐは出力、ＥＲは中性子東実効読みであり、ｇ
は中性子東実効読みから出力へ変換する係数で、出力分
布計算装置の入力値として予め用意されているものであ
る。さらに各インデックスＬ、Ｊ、にはそれぞれ、導管
、１つの導管を囲む４つの燃ｆｌ集合体、炉心高さに対
するものである。P(L, J, to) = ER(L, K)・g(L, J, K)
・・・・・・・・・(I) Here, P is the output, ER is the neutron east effective reading, and g
is a coefficient for converting neutron east effective reading to output, and is prepared in advance as an input value of the output distribution calculation device. Further, each index L, J is for a conduit, four fuel fl assemblies surrounding one conduit, and core height, respectively.
（Ｉ）式中の中性子東実効読みＥＲ（Ｌ、Ｋ）は次式に
より計算される。The neutron east effective reading ER (L, K) in formula (I) is calculated by the following formula.
ＥＲ（Ｌ、Ｋ）＝ＢＡＳＥ （Ｌ、Ｋ）＋ＤＲ（Ｌ、Ｋ
）・・・・・・・・・（ＩＩ）
ここで、ＢＡＳＥは各固定型中性子束測定器較正時に得
られる可動型中性子束測定器の読み、ＤＲは次式で求め
られるＤＲＬＰ （Ｌ、Ｎ ）を炉心高さ方向に内挿し
たものである。ER(L,K)=BASE(L,K)+DR(L,K
)・・・・・・・・・(II) Here, BASE is the reading of the movable neutron flux measuring device obtained at the time of calibration of each stationary neutron flux measuring device, and DR is the DRLP (L, N ) is interpolated in the core height direction.
ＤＲＬＰ （Ｌ、Ｎ）＝ＲＣ（Ｌ、Ｎ）−ＢＡＳＬＰ
（Ｌ、Ｎ）・・・・・・・・・（ＩＩＩ）ここで、イン
デックスＮは炉心高さ方向の固定型中性子束測定器に対
するものであり、ＲＣは固定型中性子束測定器の読み、
ＲＡＳＬＰ （Ｌ、Ｎ ）は同測定器位置でのＢＡＳＥ
値である。DRLP (L, N) = RC (L, N) - BASLP
(L, N)・・・・・・・・・(III) Here, the index N is for the fixed neutron flux measuring device in the core height direction, RC is the reading of the fixed neutron flux measuring device,
RASLP (L, N) is BASE at the same measuring instrument position.
It is a value.
以上説明したように、出力分布計算装置における出力分
布計算方法は両中性子束測定器の計算値に強く依存して
いる。中性子束測定器のうち可動型のものは通常複数個
用意されており、固定型中性子束測定器の較正時のみ使
用されるため故障を起す可能性が少ない上に、仮に故障
した場合にも可動性であるため補修交換が容易であるが
、固定型の方は原子炉の起動から停止まで１年近く高中
性子束にさらされるため、通常複数個故障している場合
が多い。As explained above, the power distribution calculation method in the power distribution calculation device is strongly dependent on the calculated values of both neutron flux measuring instruments. Among the neutron flux measuring instruments, there are usually several movable ones, and they are used only when calibrating the fixed neutron flux measuring instruments, so they are less likely to malfunction, and even if a malfunction occurs, they are movable. However, since the fixed type is exposed to high neutron flux for nearly a year from startup to shutdown of the reactor, it is common for multiple units to fail.
従来、１つあるいは複数の固定型中性子束測定器が故障
した場合、出力分布計算装置はその測定器が正常だった
時の最新の値をストアしておき、この値を用いて出力分
布の計算を行ってきた。Conventionally, when one or more fixed neutron flux measuring instruments fail, the power distribution calculation device stores the latest values when the measuring instruments were normal, and uses these values to calculate the output distribution. I've been there.
（発明が解決しようとする問題点）
しかしながら、このような出力分布計算には次のような
問題がある。すなわち、本来は炉心状態が変化している
にもかかわらず変化前の古い測定値を用いているため、
計算された出力分布の精度が良くない、特に制御棒が移
動したような出力分布が大幅に変化した場合等、最も出
力分布の精度が必要とされる時に対応できず、極端な場
合には燃料の健全性が損われる可能性もある。(Problems to be Solved by the Invention) However, such output distribution calculation has the following problems. In other words, even though the core state has changed, old measurements before the change are used.
The accuracy of the calculated power distribution is not good, especially when the power distribution changes significantly due to movement of control rods. There is also the possibility that the soundness of
本発明はかかる点に対処してなされたもので、炉心内に
配置された１つあるいは複数個の固定型中性子束測定器
が故障した場合、これを検知し、故障した固定型中性子
束測定器の計数値に代る信頼すべき代替値を与えて精度
の良い出力分布を計算することができる原子炉出力分布
監視装置を提供しようとするものである。The present invention has been made in view of this problem, and is capable of detecting a malfunction of one or more fixed neutron flux measuring devices installed in the reactor core and The present invention aims to provide a reactor power distribution monitoring device that can calculate a highly accurate power distribution by providing a reliable alternative value to the counted value of .
［発明の梢成］
（問題点を解決するための手段）
すなわち本発明は、炉心内に配置された中性子束測定器
の測定信号から出力分布を算出する原子炉出力分布監視
装置において、炉心内に配置された多数の固定型中性子
束測定器の出力信号を入力して該固定型中性子束測定器
の故障を検出し故障した固定型中性子束測定器の位置へ
可動型中性子束測定器を挿入する手段と、前記故障した
固定型中性子束測定器以外の固定型中性子束測定器およ
び故障した固定型中性子束測定器の位置に挿入された前
記可動型中性子束測定器の出力信号を入力して炉心内の
出力分布を算出する手段とを備えたことを特徴とする。[Achievements of the invention] (Means for solving the problems) In other words, the present invention provides a reactor power distribution monitoring device that calculates a power distribution from a measurement signal of a neutron flux measuring device placed in the reactor core. A movable neutron flux measuring device is inserted into the position of the failed fixed neutron flux measuring device by inputting the output signals of a large number of fixed neutron flux measuring devices placed in the fixed neutron flux measuring device to detect a failure of the fixed neutron flux measuring device. means for inputting the output signals of a fixed neutron flux measuring device other than the broken fixed neutron flux measuring device and the movable neutron flux measuring device inserted at the position of the broken fixed neutron flux measuring device; The method is characterized by comprising means for calculating the power distribution within the reactor core.
（作 用）
本発明の原子炉出力分布監視装置では、固定型中性子束
測定器の故障が検出されなかった場合には前述のように
出力分布を算出するが、故障が検出された場合には、故
障の検出された固定型中性子束測定器の位置に代わりの
可動型中性子束測定器を挿入し、出力分布は前述の（Ｉ
）式のＲＣの代替値として、挿入された可動型中性子束
測定器の計数値を使用して出力分布を算出する。(Function) In the reactor power distribution monitoring device of the present invention, if no failure is detected in the fixed neutron flux measuring device, the power distribution is calculated as described above, but if a failure is detected, the power distribution is calculated as described above. , a replacement movable neutron flux measuring device is inserted in the position of the fixed neutron flux measuring device where the failure was detected, and the output distribution is changed to the above-mentioned (I
) The output distribution is calculated using the count value of the inserted movable neutron flux measuring device as a substitute value for RC in the equation.
（実施例）
以下、図面に示す一実施例について本説明を詳細説明に
する。(Example) Hereinafter, this description will be made in detail regarding one example shown in the drawings.
第１図は本発明の一実施例の原子炉出力分布監視装置を
示すもので、原子炉１０の炉心１１内に配置された多数
の固定型中性子束測定器１および可動型中性子束測定器
５の計数値は、データサンプラ１２を介して出力分布計
算装置１３に入力される。出力分布計算装置１３はこの
計数値を、予め設定された上限値および下限値と比較し
、この範囲を逸脱するような異常な計数値を示す固定型
中性子束測定器１がある場合には、この固定型中性子束
測定器１の位置を知らせる故障検出信号を中性子束測定
器駆動装置１４に出力し、この固定型中性子束測定器１
の位置に可動型中性子束測定器５を挿入し、固定する。FIG. 1 shows a reactor power distribution monitoring device according to an embodiment of the present invention, in which a large number of fixed neutron flux measuring instruments 1 and movable neutron flux measuring instruments 5 are arranged in a core 11 of a nuclear reactor 10. The count value is input to the output distribution calculation device 13 via the data sampler 12. The output distribution calculation device 13 compares this count value with preset upper and lower limit values, and if there is a fixed neutron flux measuring device 1 that shows an abnormal count value that deviates from this range, A failure detection signal indicating the position of the fixed neutron flux measuring device 1 is output to the neutron flux measuring device driving device 14, and the fixed neutron flux measuring device 1
Insert the movable neutron flux measuring device 5 at the position and fix it.
そして、出力分布計算装置１３は、各固定型中性子束測
定器１および可動型中性子束測定器５の計数値と、入出
力装置１５から入力された計算に必要なデータから前述
の（Ｉ［［）式のＲＣの代替値として、故障している固
定型中性子束測定器１の位置へ挿入された可動型中性子
束測定器５の計数値を使用して炉心内の出力分布を計算
し、この計算結果を入出力装置１５に表示する。Then, the output distribution calculation device 13 calculates the above-mentioned (I[[ ), the power distribution in the reactor core is calculated using the count value of the movable neutron flux measuring device 5 inserted in the position of the fixed neutron flux measuring device 1 that is out of order. The calculation results are displayed on the input/output device 15.
また、炉心１１内に多数配置された固定型中性子束測定
器１のうち１個も故障が発生していない場合には、出力
分布計算装置１３は通常の計算プロセスに従って出力分
布を計算する。Further, if no failure has occurred in any of the fixed neutron flux measuring devices 1 arranged in the reactor core 11, the power distribution calculation device 13 calculates the power distribution according to a normal calculation process.
したがって、この実施例の原子炉出力分布監視装置では
、炉心内の固定型中性子束測定器１のうちいくつかが故
障した場合でも、これらの測定器が正しく動作している
時と同じく精度の良い出力分布を計算することができる
。Therefore, in the reactor power distribution monitoring system of this embodiment, even if some of the fixed neutron flux measuring devices 1 in the reactor core fail, the system can still maintain the same level of accuracy as when these measuring devices are operating correctly. Power distribution can be calculated.
なお、本実施例における故障検出は、入力した計算値が
、予め設定された上限および下限値の範囲を逸脱したも
のを異常と判断し、これを検出するものであるが、故障
検出方法としては、例えば特許第１２０７７２９号に提
案されているように、各中性子束測定器の計数値の時間
平均値によって規格したものの偏差値を算出し、この偏
差値の標準がらの異常な偏りを検出することによって故
障を検出する方法あるいは、特開昭５５−７６４４号に
提案されているように、中性子束測定器に用いられる中
性子検出物質の消耗による測定器の感度減衰係数の標準
からの異常な偏りを検出することによって故障を検出す
る方法等を使用することもできる。In addition, in the fault detection in this embodiment, if the input calculated value deviates from the range of preset upper and lower limit values, it is judged as an abnormality and this is detected. However, as a fault detection method, For example, as proposed in Japanese Patent No. 1207729, the deviation value of the normalized value of the count value of each neutron flux measuring device is calculated by the time average value, and the abnormal deviation from the standard of this deviation value is detected. Alternatively, as proposed in Japanese Patent Application Laid-Open No. 55-7644, it is possible to detect abnormal deviations from the standard in the sensitivity attenuation coefficient of the measuring instrument due to consumption of the neutron detection material used in the neutron flux measuring instrument. It is also possible to use a method of detecting a failure by detecting it.
この場合、本発明の装置はより効率的に動作する。In this case, the device of the invention operates more efficiently.
また、故障している固定型中性子束測定器の代りに固定
型中性子束測定器の較正に用いる可動型中性子束測定器
を使用するとしたが、固定型中性子束測定器と同型の可
動型中性子束測定器を複数個予備として用意してこれを
使用するようにしても同様な効果が得られる。In addition, we decided to use a movable neutron flux meter used for calibrating the fixed neutron flux meter in place of the malfunctioning fixed neutron flux meter. A similar effect can be obtained by preparing a plurality of spare measuring instruments and using them.
［発明の効果］
以上の説明からも明らかなように、本発明の出力分布監
視装置によれば、炉心内に配置された固定型中性子束測
定器がいくつか故障した場合でも、これらの測定器が正
常に作動している時と同様に精度の良い出力分布を求め
ることができ、燃料の健全性の評価および炉心状態の把
握を正しく行うことができる。また、制御棒パターン交
換時のような大幅に炉心状態が変化する場合にも、炉心
を正確に監視することができるため、稼動率の向上にも
寄与する。[Effects of the Invention] As is clear from the above explanation, according to the power distribution monitoring device of the present invention, even if some of the fixed neutron flux measuring devices arranged in the reactor core fail, these measuring devices can be It is possible to obtain the same accurate power distribution as when the reactor is operating normally, and it is possible to accurately evaluate the health of the fuel and understand the state of the reactor core. Furthermore, even when the core condition changes significantly, such as during control rod pattern exchange, the core can be accurately monitored, contributing to improved operating efficiency.
第１は本発明の原子炉出力分布監視装置の一実施例を示
す構成図、第２図は炉心の一部を示す側面図、第３図は
第２図の上面図である。
１・・・・・・・・・固定型中性子束測定器４・・・・
・・・・・可動型中性子束測定器１１・・・・・・・・
・炉心
１３・・・・・・・・・出力分布計算装置１４・・・・
・・・・・中性子束測定器駆動装置出願人 日
本原子力事業株式会社出願人 株式会社 東
芝
代理人 弁護士 須 山 佐 −
第１図
第２図1 is a configuration diagram showing one embodiment of the reactor power distribution monitoring device of the present invention, FIG. 2 is a side view showing a part of the reactor core, and FIG. 3 is a top view of FIG. 2. 1...Fixed neutron flux measuring instrument 4...
...Moveable neutron flux measuring device 11...
・Core 13......Power distribution calculation device 14...
...Neutron flux measuring device drive device Applicant: Japan Atomic Energy Corporation Applicant: Higashi Co., Ltd.
Lawyer Suyama, representing Shiba - Figure 1 Figure 2
Claims (1)
ら出力分布を算出する原子炉出力分布監視装置において
、炉心内に配置された多数の固定型中性子束測定器の出
力信号を入力して該固定型中性子束測定器の故障を検出
し故障した固定型中性子束測定器の位置へ可動型中性子
束測定器を挿入する手段と、前記故障した固定型中性子
束測定器以外の固定型中性子束測定器および故障した固
定型中性子束測定器の位置に挿入された前記可動型中性
子束測定器の出力信号を入力して炉心内の出力分布を算
出する手段とを備えたことを特徴とする原子炉出力分布
監視装置。(1) In a reactor power distribution monitoring device that calculates the power distribution from the measurement signals of neutron flux measuring devices placed in the reactor core, the output signals of a large number of fixed neutron flux measuring devices placed in the reactor core are input. means for detecting a failure in the fixed neutron flux measuring device and inserting a movable neutron flux measuring device into the position of the broken fixed neutron flux measuring device; The method is characterized by comprising a flux measuring device and a means for calculating the power distribution in the core by inputting the output signal of the movable neutron flux measuring device inserted at the position of the fixed neutron flux measuring device that has failed. Reactor power distribution monitoring device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61255393A JPS63109396A (en) | 1986-10-27 | 1986-10-27 | Monitor for output distribution of nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61255393A JPS63109396A (en) | 1986-10-27 | 1986-10-27 | Monitor for output distribution of nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63109396A true JPS63109396A (en) | 1988-05-14 |
Family
ID=17278138
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61255393A Pending JPS63109396A (en) | 1986-10-27 | 1986-10-27 | Monitor for output distribution of nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63109396A (en) |
-
1986
- 1986-10-27 JP JP61255393A patent/JPS63109396A/en active Pending
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