JPS62479B2 - - Google Patents
Info
- Publication number
- JPS62479B2 JPS62479B2 JP53036117A JP3611778A JPS62479B2 JP S62479 B2 JPS62479 B2 JP S62479B2 JP 53036117 A JP53036117 A JP 53036117A JP 3611778 A JP3611778 A JP 3611778A JP S62479 B2 JPS62479 B2 JP S62479B2
- Authority
- JP
- Japan
- Prior art keywords
- lprm
- count value
- count
- rate
- output
- 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
Links
- 230000005856 abnormality Effects 0.000 claims description 10
- 230000006866 deterioration Effects 0.000 claims description 9
- 238000012935 Averaging Methods 0.000 claims description 4
- 238000009835 boiling Methods 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 2
- 238000010586 diagram Methods 0.000 description 6
- 238000003745 diagnosis Methods 0.000 description 4
- 230000002159 abnormal effect Effects 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 230000007423 decrease Effects 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000035945 sensitivity Effects 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)
Description
【発明の詳細な説明】
本発明は沸騰水型原子炉に係り、特に炉内中性
子計装(Local Power Range Monitor;以下
LPRMと称する。)の異常診断の技術に関する。[Detailed Description of the Invention] The present invention relates to boiling water nuclear reactors, and particularly to in-reactor neutron instrumentation (Local Power Range Monitor; hereinafter referred to as
It is called LPRM. ) related to abnormality diagnosis technology.
LPRMは炉心内の中性子束を測定し、その測定
値はプロセス計算機に入力され、いわゆる炉心性
能計算により炉心内出力分布、燃焼度分布等の計
算に用いられる重要な基本入力である。ところが
LPRMは原子炉内の放射線、高温等の悪環境によ
り性能が時間的に変化していく。 LPRM measures the neutron flux inside the reactor core, and the measured value is input into a process computer, which is an important basic input used for calculating the power distribution, burnup distribution, etc. in the core in so-called core performance calculations. However
The performance of LPRM changes over time due to the adverse environment such as radiation and high temperature inside the reactor.
LPRMの性能のうち、U235の劣化による性能の
変化は計算により補正できるが、それ以外の原因
による性能の変化は一般的にゆつくりした場合が
多く断線のような明確な故障でないため運転員が
異常を判断することは従来困難であつた。 Among LPRM performance changes, changes in performance due to U 235 deterioration can be corrected by calculation, but changes in performance due to other causes are generally slow and do not require operator intervention since they are not obvious failures such as disconnections. Until now, it has been difficult to determine whether there is an abnormality.
第1図に、LPRMの計数値RPの例を示す。第
1図イは健全なLPRMの例で、LPRMのU235の劣
化により時間tと共に単調に減少している。第1
図ロは健全でないLPRMの例で、U235の劣化にも
かかわらず計算値RPが時間tと共に増加してい
るので、LPRM異常と判定できる。問題はこれら
の変化が時間的にゆつくりしたもので、日ないし
週のオーダーであるため、判定がしにくいことで
ある。 FIG. 1 shows an example of the count value RP of LPRM. Figure 1A shows an example of a healthy LPRM, in which it monotonically decreases with time t due to the deterioration of U 235 in the LPRM. 1st
Figure B is an example of an unhealthy LPRM, in which the calculated value RP increases with time t despite the deterioration of U 235 , so it can be determined that the LPRM is abnormal. The problem is that these changes occur slowly over time, on the order of days or weeks, making it difficult to judge.
本発明は上述の事情を考慮してなされたもの
で、LPRMが時間的に異常に変化した場合にただ
ちにその異常を発見、判定し、運転員に警報を出
すことを目的としている。 The present invention has been made in consideration of the above-mentioned circumstances, and an object of the present invention is to immediately discover and determine the abnormality when the LPRM changes abnormally over time, and issue a warning to the operator.
以下図面を参照して本発明の一実施例を説明す
る。第2図は本発明の中性子計装異常診断装置の
構成を示す説明図であり、矢印は入力の流れを示
す。 An embodiment of the present invention will be described below with reference to the drawings. FIG. 2 is an explanatory diagram showing the configuration of the neutron instrumentation abnormality diagnosis apparatus of the present invention, and arrows indicate input flows.
炉心1にLPRM2は通常100個程度配置されて
いる。LPRM2の計数値は温度、圧力等のプラン
トデータと共に炉心性能計算装置3に入力され、
炉心性能計算装置で計算された燃焼度が、LPRM
劣化補正装置4に入力される。また、LPRM2の
計数値はLPRM劣化補正装置4で補正され出力規
格化装置5で規格化されて、LPRM計数記憶装置
6に適切な時間間隔で入力される。その後、
LPRM計数平均化装置7により計数値の時間変化
率を計算し、変化率判定装置8で判定し、変化率
が正または負の場合、警報装置9を作動させる。 Normally, about 100 LPRM2 are arranged in the core 1. The counted values of LPRM2 are input into the core performance calculation device 3 along with plant data such as temperature and pressure.
The burnup calculated by the core performance calculation device is LPRM.
The signal is input to the deterioration correction device 4. Further, the count value of the LPRM2 is corrected by the LPRM deterioration correction device 4, normalized by the output standardization device 5, and inputted to the LPRM count storage device 6 at appropriate time intervals. after that,
The LPRM count averaging device 7 calculates the rate of change over time of the count value, and the rate of change determining device 8 determines the rate of change. If the rate of change is positive or negative, the alarm device 9 is activated.
LPRM劣化補正装置4では、炉心性能計算装置
3で計算した燃焼度EによりLPRM2のU235の劣
化による計数値RPの減少を次のようにして補正
する。 The LPRM deterioration correction device 4 corrects the decrease in the count value RP due to the deterioration of U 235 of the LPRM 2 using the burnup E calculated by the core performance calculation device 3 as follows.
aを定数として、LPRMの感度SはS=e-aE
の形で劣化するので、補正後の計数値RCは、原
子炉出力が一定の場合、
RC=RP/S
となる。 With a as a constant, the sensitivity S of LPRM is S=e -aE
Therefore, when the reactor output is constant, the corrected count value RC becomes RC=RP/S.
原子炉出力が変化する場合は出力規格化装置5
で、原子炉出力の変動を補正する。すなわち、時
間0の時の出力を1.0と規格化しておき、任意の
時間での原子炉出力をCTPとすると、計数値RC
は
RC=RP/S×CTP
となる。 If the reactor output changes, the output standardization device 5
to compensate for fluctuations in reactor output. In other words, if the output at time 0 is normalized to 1.0 and the reactor output at any time is CTP, then the count value RC
becomes RC=RP/S×CTP.
LPRMの物理的(核的)性質からRCは第3図
に示すように時間tに対して一定である。 Due to the physical (nuclear) properties of LPRM, RC is constant with respect to time t, as shown in FIG.
上述のように計算されたRCの値をLPRM計数
記憶装置6により時間的に適切な間隔で記憶す
る。この間隔は、通常1時間おきで数目間程度を
記憶しておく事が望ましい。 The RC value calculated as described above is stored in the LPRM count storage device 6 at appropriate time intervals. It is desirable to memorize this interval, usually every hour, for a few seconds.
第4図は計数値RCと記憶されている計数値デ
ータの数Nを示す。次に、LPRM計数平均化装置
7によりRCの時間変化を求める。その方法とし
ては、第4図に示すデータを1次直線
RC=at+b (a、b、定数、t:時間)
で最小二乗法により求め、係数aが0もしくは0
に近い小さい値か否で判定する。例えば、第1図
ロに示すようなLPRMの計数値の場合はa>0と
なり変化率判定装置により異常と判定され、警報
装置9により判定結果をただちに運転員等に知ら
せる。 FIG. 4 shows the count value RC and the number N of stored count value data. Next, the LPRM count averaging device 7 determines the change in RC over time. The method is to obtain the data shown in Figure 4 using the least squares method using a linear straight line RC = at + b (a, b, constant, t: time), and if the coefficient a is 0 or 0.
It is determined whether the value is small or close to . For example, in the case of the LPRM count value as shown in FIG.
以上説明したように、本発明の中性子計装異常
診断装置によれば、時間的に変動するLPRMのデ
ータを選択する事により、確実かつ容易にLPRM
の異常を発見し、判定し、運転員に通報でき、原
子炉の安全性が向上する。 As explained above, according to the neutron instrumentation abnormality diagnosis device of the present invention, by selecting time-varying LPRM data, LPRM can be reliably and easily performed.
It is possible to discover abnormalities in nuclear reactors, judge them, and report them to operators, improving the safety of nuclear reactors.
第1図イは健全なLPRM、ロは異常なLPRMの
計数値と時間の関係を示す説明図、第2図は本発
明の中性子計装異常診断装置の構成を示す説明
図、第3図は係数値RCと時間tの関係を示す説
明図、第4図は計数値RCと、LPRM計数記憶装
置に記憶されているデータの数Nの関係を示す説
明図である。
1……炉心、2……LPRM、3……炉心性能計
算装置、4……LPRM劣化補正装置、5……出力
規格化装置、6……LPRM係数記憶装置、7……
LPRM計数平均化装置、8……変化率判定装置、
9……警報装置。
Figure 1A is an explanatory diagram showing the relationship between the count value and time of a healthy LPRM, B is an abnormal LPRM, Figure 2 is an explanatory diagram showing the configuration of the neutron instrumentation abnormality diagnosis device of the present invention, and Figure 3 is an explanatory diagram showing the relationship between the count value and time of an abnormal LPRM. FIG. 4 is an explanatory diagram showing the relationship between the coefficient value RC and time t. FIG. 4 is an explanatory diagram showing the relationship between the count value RC and the number N of data stored in the LPRM count storage device. 1... Core, 2... LPRM, 3... Core performance calculation device, 4... LPRM deterioration correction device, 5... Output standardization device, 6... LPRM coefficient storage device, 7...
LPRM count averaging device, 8...change rate determination device,
9...Alarm device.
Claims (1)
心性能計算装置に入力して燃焼度を求め、燃焼度
およびLPRM計数値をLPRM劣化補正装置に入力
して補正されたLPRM計数値を出力規格化装置で
規格化し、出力規格化装置の出力データを適切な
時間間隔でLPRM計数記憶装置に記憶させ、この
データからLPRM計数値の変化率をLPRM計数平
均化装置で計算し、変化率判定装置でLPRMの異
常を判定し、警報装置によりLPRMの異常を通報
することを特徴とする中性子計装異常診断装置。1 In a boiling water reactor, input the LPRM count value into the core performance calculation device to determine burnup, input the burnup and LPRM count value into the LPRM deterioration correction device, and standardize the corrected LPRM count value for output. The output data of the output standardization device is stored in the LPRM count storage device at appropriate time intervals, the rate of change of the LPRM count value is calculated from this data by the LPRM count averaging device, and the rate of change determination device calculates the rate of change of the LPRM count value from this data. A neutron instrumentation abnormality diagnostic device characterized by determining an abnormality in an LPRM and notifying the abnormality of the LPRM by an alarm device.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3611778A JPS54129295A (en) | 1978-03-30 | 1978-03-30 | Diagnostics device of neutron instrumentation abnormality |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3611778A JPS54129295A (en) | 1978-03-30 | 1978-03-30 | Diagnostics device of neutron instrumentation abnormality |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS54129295A JPS54129295A (en) | 1979-10-06 |
JPS62479B2 true JPS62479B2 (en) | 1987-01-08 |
Family
ID=12460827
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP3611778A Granted JPS54129295A (en) | 1978-03-30 | 1978-03-30 | Diagnostics device of neutron instrumentation abnormality |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS54129295A (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP3875838B2 (en) * | 1998-04-28 | 2007-01-31 | アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング | Method and apparatus for monitoring power increase during reactor start-up |
-
1978
- 1978-03-30 JP JP3611778A patent/JPS54129295A/en active Granted
Also Published As
Publication number | Publication date |
---|---|
JPS54129295A (en) | 1979-10-06 |
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