JPH0830749B2 - Control rod withdrawal monitoring device - Google Patents
Control rod withdrawal monitoring deviceInfo
- Publication number
- JPH0830749B2 JPH0830749B2 JP63039585A JP3958588A JPH0830749B2 JP H0830749 B2 JPH0830749 B2 JP H0830749B2 JP 63039585 A JP63039585 A JP 63039585A JP 3958588 A JP3958588 A JP 3958588A JP H0830749 B2 JPH0830749 B2 JP H0830749B2
- Authority
- JP
- Japan
- Prior art keywords
- neutron flux
- control rod
- local
- output
- detection signal
- 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 - Fee Related
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)
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、沸騰水型原子炉における制御棒の引抜きに
よる局部出力上昇を監視する制御棒引抜き監視装置に関
する。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application] The present invention relates to a control rod withdrawal monitoring device for monitoring a local output increase due to withdrawal of a control rod in a boiling water reactor.
（従来の技術） 沸騰水型原子炉の炉心には、多数の燃料集合体が配置
されるとともにこれら燃料集合体の間に制御棒が規則的
に配置されている。これら制御棒は核分裂の連鎖反応を
制御するものであるが、原子炉の出力を所定値に維持す
るために多数の制御棒のうちから所定の制御棒が引抜か
れる。このように制御棒が引抜かれると、この引抜かれ
た制御棒付近の連鎖反応が多くなって局部的に出力が上
昇する。この局部出力の上昇が高すぎると原子炉の運転
に支障を来たす恐れがあるので、制御棒の引抜きによる
局部出力が監視されている。(Prior Art) A large number of fuel assemblies are arranged in the core of a boiling water reactor, and control rods are regularly arranged between these fuel assemblies. These control rods control the chain reaction of nuclear fission, but a predetermined control rod is pulled out from a large number of control rods in order to maintain the output of the reactor at a predetermined value. When the control rod is pulled out in this way, the chain reaction near the pulled-out control rod increases and the output locally rises. If this rise in local power is too high, it may interfere with the operation of the reactor, so the local power due to pulling out the control rod is monitored.
ところで、かかる制御棒引抜きによる局部出力上昇の
監視は次のように行なわれている。第３図は沸騰水型原
子炉の炉心の断面図であって、上部に全体断面図を示
し、下部に部分拡大図を示してある。ここで、説明を簡
単にするために部分拡大図を参照して説明する。この部
分拡大図は炉心における座標（13〜27,9〜23）の断面を
示しており、燃料集合体１が規則的に配列されるととも
にこれら燃料集合体１の間に規則的に制御棒２が配置さ
れている。そして、中性子束検出器３がそれぞれ制御棒
２を２本づつ毎に配置されている。従って、中性子束検
出器３が４本で制御棒２の４本を囲む如く配置されてい
る。なお、これら中性子束検出器３は第４図に示すよう
に検出用管４の内部にそれぞれ各検出器５−１〜５−４
が設けられたものとなっており、各検出器５−１〜５−
４はそれぞれ他の中性子束検出器３における各検出器と
炉心内において同一平面上に配置されている。By the way, the monitoring of the local output increase by pulling out the control rod is performed as follows. FIG. 3 is a cross-sectional view of the core of a boiling water nuclear reactor, in which an overall cross-sectional view is shown in the upper part and a partially enlarged view is shown in the lower part. Here, in order to simplify the description, description will be given with reference to a partially enlarged view. This partially enlarged view shows a cross section of coordinates (13 to 27, 9 to 23) in the core, in which the fuel assemblies 1 are regularly arranged and the control rods 2 are regularly arranged between the fuel assemblies 1. Are arranged. The neutron flux detectors 3 are arranged every two control rods 2. Therefore, four neutron flux detectors 3 are arranged so as to surround four of the control rods 2. As shown in FIG. 4, these neutron flux detectors 3 are provided inside the detection tube 4, respectively.
Is provided, and each detector 5-1 to 5-
4 are arranged on the same plane as the detectors of the other neutron flux detectors 3 in the core.
しかして、このように構成された炉心内において座標
（22,18）の制御棒２つまり制御棒2aが引抜かれると、
この制御棒2aの引抜きによる局部出力を監視するために
この制御棒2aを囲む４つの中性子束検出3,つまり座標
（24,20）（16,20）（16,12）（24,12）の中性子束検出
器３が選択される。そして、これら選択された中性子束
検出器３からの各中性子束検出信号の加算平均値が求め
られ、この後この平均値に基づいて局部出力の上昇が監
視される。Then, when the control rod 2 at the coordinates (22,18), that is, the control rod 2a is pulled out in the core configured in this way,
In order to monitor the local output by pulling out this control rod 2a, four neutron flux detections 3 surrounding this control rod 2a, that is, coordinates (24,20) (16,20) (16,12) (24,12) The neutron flux detector 3 is selected. Then, an average value of the neutron flux detection signals from the selected neutron flux detectors 3 is calculated, and thereafter, the rise of the local output is monitored based on this average value.
しかしながら、このような監視の方法では各中性子束
検出信号の加算平均値を用いているので、局部出力の上
昇が顕著に現れないという問題がある。つまり、制御棒
2aが引抜かれた場合、これによる局部出力上昇の影響が
最も現れるのは座標（24,20）の中性子束検出器３であ
るが、この中性子束検出器３の中性子束検出信号が局部
出力上昇の影響の現れない他の中性子束検出器３の中性
子束検出信号と単に加算平均されるので、その局部出力
上昇が相殺されるからである。However, in such a monitoring method, since the averaging value of each neutron flux detection signal is used, there is a problem that the local output does not increase remarkably. That is, the control rod
When 2a is pulled out, the effect of the local output increase due to this is most apparent in the neutron flux detector 3 at coordinates (24, 20), but the neutron flux detection signal of this neutron flux detector 3 causes the local output increase. This is because the neutron flux detection signals of the other neutron flux detectors 3 which do not show the influence of (3) are simply added and averaged, and the local output increase is offset.
（発明が解決しようとする課題） 以上のように制御棒引抜きによる局部出力上昇が正確
に監視できなかった。(Problems to be Solved by the Invention) As described above, the local output increase due to the withdrawal of the control rod cannot be accurately monitored.
そこで本発明は、制御棒引抜きによる局部出力上昇を
正確に監視できる制御棒引抜き監視装置を提供すること
を目的とする。Therefore, it is an object of the present invention to provide a control rod withdrawal monitoring device capable of accurately monitoring a local output increase due to control rod withdrawal.
［発明の構成］ （課題を解決するための手段） 本発明は、原子炉炉心内に配列された多数の燃料集合
体の間に規則的に配置された制御棒を引抜いたときに生
じる局部的な出力上昇を原子炉炉心内に配置された各中
性子束検出器からの中性子束検出信号を受けて監視する
制御棒引抜き監視装置において、引抜かれる制御棒を囲
む如く配置された各中性子束検出器からの中性子束検出
信号を選択して取込み，これら中性子束検出信号に対し
て選択された各中性子束検出器への制御棒の引抜きによ
る中性子束の影響度を加えて各中性子束検出信号の平均
値を求める局部平均算出手段と、この局部平均算出手段
で求められた局部中性子束平均値に基づいて局部出力上
昇の判定を行う局部出力判定手段とを備えて上記目的を
達成しようとする制御棒引抜き監視装置である。[Means for Solving the Problems] (Means for Solving the Problems) The present invention is directed to a local problem that occurs when a control rod regularly arranged between a large number of fuel assemblies arranged in a reactor core is pulled out. Control rod pull-out monitoring device for monitoring the output rise by receiving neutron flux detection signals from each neutron flux detector placed in the reactor core, each neutron flux detector placed so as to surround the control rod to be pulled out Select the neutron flux detection signals from the neutron flux detection signal, and add the influence of the neutron flux by pulling out the control rod to each selected neutron flux detection signal to these neutron flux detection signals A control rod for achieving the above object, which includes a local average calculating means for obtaining a value and a local output determining means for determining a local output increase based on the local neutron flux average value obtained by the local average calculating means. Pull It is a gas monitoring device.
（作用） このような手段を備えたことにより、制御棒が引抜か
れると局部平均算出手段によりこの制御棒を囲む如く配
置された各中性子束検出器からの中性子束検出信号が選
択され，これら中性子束検出信号に対して制御棒の引抜
きによる中性子束の影響度を加えて各中性子束検出信号
の平均値が求められ、この求められた局部中性子束平均
値に基づいて局部出力判定手段により局部出力上昇が判
定される。(Operation) With the provision of such means, when the control rod is pulled out, the neutron flux detection signals from the neutron flux detectors arranged so as to surround the control rod are selected by the local average calculation means, and these neutron flux detection signals are selected. The average value of each neutron flux detection signal is obtained by adding the influence of the neutron flux due to the extraction of the control rod to the flux detection signal, and the local output by the local output determination means based on the obtained local neutron flux average value A rise is determined.
（実施例） 以下、本発明の一実施例について図面を参照して説明
する。(Example) Hereinafter, one example of the present invention will be described with reference to the drawings.
第１図は制御棒引抜き監視装置の全体構成図である。
なお、説明の度合い上第３図を参照する。中性子束検出
器３の各検出器から出力される中性子束検出信号はそれ
ぞれ局部出力モニタ６−1,6−2,…６−ｎに送られると
ともに一括して平均出力モニタ７に送られている。各局
部出力モニタ６−１〜６−ｎはそれぞれ中性子束検出信
号を受けて中性子束を監視するとともに中性子束検出信
号に対応した信号を制御棒引抜き監視装置８の局部出力
選択算出部９へ送出するものである。又、平均出力モニ
タ７は全中性子束検出信号を受けて加算平均して炉心内
における平均中性子束を算出する機能を有するものであ
る。FIG. 1 is an overall configuration diagram of a control rod pull-out monitoring device.
Note that FIG. 3 is referred to for the sake of explanation. The neutron flux detection signals output from the detectors of the neutron flux detector 3 are sent to the local output monitors 6-1, 6-2, ... 6-n, respectively, and are also sent to the average output monitor 7 collectively. . Each of the local output monitors 6-1 to 6-n receives the neutron flux detection signal to monitor the neutron flux and sends a signal corresponding to the neutron flux detection signal to the local output selection calculation unit 9 of the control rod pull-out monitoring device 8. To do. The average output monitor 7 has a function of calculating the average neutron flux in the core by receiving the total neutron flux detection signals and averaging them.
さて、局部出力選択算出部９は、原子炉手動制御装置
10からの制御棒選択信号Ｑを受けて引抜かれる制御棒を
囲む如く配置された４つの中性子束検出器からの各中性
子束検出信号を選択して取込み，これら中性子束検出信
号に対して選択された各中性子束検出器への制御棒の引
抜きによる中性子束の影響度を加えて各中性子束検出信
号の平均値つまり局部中性子束平均値を求める局部平均
算出手段としての機能を有するものである。具体的に第
３図に示す制御棒s1が引抜かれれば４つの中性子束検出
器p1〜p4が選択され、又制御棒s2が引抜かれれば４つの
中性子束検出器p1,p2,p5,p6が選択される。又、局部中
性子束平均値の算出は次の通り行なわれる。すなわち、
第２図に示すように４つの中性子束検出器3a,3b,3c,3d
に囲まれた制御棒2bが引抜かれた場合を考えると、各中
性子束検出器3a〜3dのそれぞれの間の距離を「４」とす
れば各中性子束検出器3cと3dとを結ぶ線分に制御棒2bか
ら垂線を下ろすと各中性子束検出器3c,3d間は「3:1」に
分割される。これにより、中性子束検出器3cと制御棒2b
との距離は となり、又中性子束検出器3dと制御棒2bとの距離は となる。しかして、各中性子束検出器3a,3b,3c,3dから
制御棒2bまでの距離の比は となり、簡単にして となる。よって、比重は となる。かくして、局部中性子束平均値はこれら比重を
それぞれ各中性子束検出器3a,3b,3c,3dから出力される
各中性子束検出信号に乗算して加算し、この加算値を前
記比重の和で除算して求められる。そうして、このよう
にして求められた局部中性子束平均値を示す局部中性子
束平均信号ｋは局部出力判定手段11に送られている。Now, the local output selection calculation unit 9 is a reactor manual control device.
Upon receiving the control rod selection signal Q from 10 and extracting the neutron flux detection signals from the four neutron flux detectors arranged so as to surround the control rod to be extracted, the neutron flux detection signals are selected and selected for these neutron flux detection signals. Further, it has a function as a local average calculating means for adding the degree of influence of the neutron flux by pulling out the control rod to each neutron flux detector to obtain the average value of each neutron flux detection signal, that is, the local neutron flux average value. Specifically, if the control rod s1 shown in FIG. 3 is withdrawn, four neutron flux detectors p1 to p4 are selected, and if the control rod s2 is withdrawn, four neutron flux detectors p1, p2, p5, p6 is selected. Further, the calculation of the local neutron flux average value is performed as follows. That is,
As shown in Fig. 2, four neutron flux detectors 3a, 3b, 3c, 3d
Considering the case where the control rod 2b surrounded by is extracted, if the distance between the neutron flux detectors 3a to 3d is "4", the line segment connecting the neutron flux detectors 3c and 3d When the perpendicular line is drawn from the control rod 2b, the space between the neutron flux detectors 3c and 3d is divided into "3: 1". As a result, the neutron flux detector 3c and the control rod 2b
And the distance And the distance between the neutron flux detector 3d and the control rod 2b is Becomes Then, the ratio of the distance from each neutron flux detector 3a, 3b, 3c, 3d to the control rod 2b is And make it easy Becomes Therefore, the specific gravity is Becomes Thus, the local neutron flux average value, these specific gravity is multiplied by each neutron flux detection signal output from each neutron flux detector 3a, 3b, 3c, 3d and added, this added value is divided by the sum of the specific gravity Is required. Then, the local neutron flux average signal k indicating the local neutron flux average value thus obtained is sent to the local output determination means 11.
この局部出力判定手段11は局部中性子束平均値に基づ
いて局部出力上昇の判定を行う機能を有するもので、利
得算出部12,利得乗算部13、トリップレベル算出部14及
びトリップ判定部15から構成されている。利得算出部12
は局部中性子束平均信号ｋ及び平均出力モニタ７からの
平均出力信号ｅとを受けてこの平均出力信号ｅを比較信
号として局部中性子束平均値の利得、つまりk/eを算出
する機能を持ったものであり、利得乗算部13は利得k/e
を局部中性子束平均信号ｋに対して乗算して局部出力信
号ｒとして送出する機能を持ったものである。一方、ト
リップレベル算出部14は、原子炉に供給される一次冷却
水の流量を測定する流量変換器16からの流量検出信号を
受け、一次冷却水の流量に応じた局部出力のトリップレ
ベルtpに変換して送出する機能を有するものである。ト
リップ判定部15は局部出力信号ｒ及びトリップレベルtp
を受けて局部出力信号ｒのレベルがトリップレベルtp以
上であれば制御棒引抜き阻止信号Ｗを原子炉手動制御装
置10へ送出する機能を持ったものである。This local output determination means 11 has a function of determining a local output increase based on the local neutron flux average value, and comprises a gain calculation unit 12, a gain multiplication unit 13, a trip level calculation unit 14, and a trip determination unit 15. Has been done. Gain calculator 12
Has a function of receiving the local neutron flux average signal k and the average output signal e from the average output monitor 7 and using this average output signal e as a comparison signal to calculate the gain of the local neutron flux average value, that is, k / e. The gain multiplication unit 13 has a gain k / e
Is multiplied by the local neutron flux average signal k and sent as a local output signal r. On the other hand, the trip level calculation unit 14 receives the flow rate detection signal from the flow rate converter 16 that measures the flow rate of the primary cooling water supplied to the reactor, and outputs the trip level tp of the local output according to the flow rate of the primary cooling water. It has a function of converting and transmitting. The trip determination unit 15 uses the local output signal r and the trip level tp.
In response, if the level of the local output signal r is equal to or higher than the trip level tp, it has a function of sending the control rod withdrawal prevention signal W to the manual reactor control device 10.
次に上記の如く構成された装置の作用について説明す
る。Next, the operation of the apparatus configured as described above will be described.
第３図に示す制御棒2aが引抜かれると、この制御棒2a
が引抜かれたことを示す制御棒選択信号Ｑが原子炉手動
制御装置10から局部出力選択算出部９に送られる。この
局部出力選択算出部９は入力した制御棒選択信号Ｑから
制御棒2aを囲む４つの中性子束検出器、つまり座標（2
4,20）（16,20）（16,12）（24,12）の中性子束検出器
３を選択し、これら中性子束検出器３からの各中性子束
検出信号を入力する。そして、座標（24,20）の中性子
束検出器３の中性子束検出信号に対して比重「１」を乗
算し、座標（16,22）の中性子束検出器３の中性子束検
出信号に対して比重 を乗算し、座標（16,12）の中性子束検出器３の中性子
束検出信号に対して比重「1/3」を乗算し、さらに座標
（24,12）の中性子束検出器３の中性子束検出信号に対
して比重 を乗算する。さらに、これら比重の乗算値を加算し、こ
の加算値を比重の和で除算して局部中性子束平均値を求
めてその局部中性子束平均信号ｋを送出する。具体的に
例えば、制御棒2aの引抜きにより座標（24,20）の中性
子束検出器３の中性子束検出信号が「10」から「100」
へ、座標（16,22）の中性子束検出器３の中性子束検出
信号が「50」から「100」へ、座標（16,12）の中性子束
検出器３の中性子束検出信号が「100」から「120」へ、
さらに座標（24,12）の中性子束検出器３の中性子束検
出信号が「50」から「100」へ変化すると、局部中性子
束平均値は「39.5」から「103」へ変化する。なお、単
に加算平均すると、局部中性子束平均値は「52.5」から
「105」への変化となる。つまり、変化の倍率が大きく
異なる。When the control rod 2a shown in FIG. 3 is pulled out, this control rod 2a
A control rod selection signal Q indicating that is extracted is sent from the nuclear reactor manual control device 10 to the local output selection calculation unit 9. This local output selection calculation unit 9 receives four neutron flux detectors surrounding the control rod 2a from the input control rod selection signal Q, that is, coordinates (2
4, 20) (16, 20) (16, 12) (24, 12) neutron flux detectors 3 are selected, and the neutron flux detection signals from these neutron flux detectors 3 are input. Then, the neutron flux detection signal of the neutron flux detector 3 at the coordinates (24, 20) is multiplied by the specific gravity “1”, and the neutron flux detection signal of the neutron flux detector 3 at the coordinates (16, 22) is detected. specific gravity And the neutron flux detection signal of the neutron flux detector 3 at coordinates (16,12) is multiplied by the specific gravity "1/3", and the neutron flux of the neutron flux detector 3 at coordinates (24,12) is further multiplied. Specific gravity for detection signal Multiply by Further, the multiplied values of these specific gravities are added, this added value is divided by the sum of the specific gravities to obtain the local neutron flux average value, and the local neutron flux average signal k is transmitted. Specifically, for example, when the control rod 2a is pulled out, the neutron flux detection signal of the neutron flux detector 3 at the coordinates (24,20) is changed from "10" to "100".
, The neutron flux detection signal of the neutron flux detector 3 at coordinates (16,22) is changed from "50" to "100", and the neutron flux detection signal of the neutron flux detector 3 at coordinates (16,12) is "100". From "120",
Further, when the neutron flux detection signal of the neutron flux detector 3 at the coordinates (24, 12) changes from "50" to "100", the local neutron flux average value changes from "39.5" to "103". Note that the local neutron flux average value changes from "52.5" to "105" when simply averaged. That is, the rate of change is significantly different.
又、このとき平均出力モニタ７は全ての中性子束検出
器３からの各中性子束検出信号を受けて加算し、この加
算値を中性子束検出器３の本数で除算して平均出力信号
ｅを送出している。しかして、利得算出部12は局部中性
子束平均信号ｋを平均出力信号ｅで除算して局部中性子
束平均の利得k/eを求め、次に利得乗算部13はこの利得k
/eを受けて局部中性子束平均信号ｋに乗算し、この乗算
値を局部出力ｒとしてトリップ判定部15に送出する。At this time, the average output monitor 7 receives the neutron flux detection signals from all the neutron flux detectors 3 and adds them, divides the added value by the number of neutron flux detectors 3 and sends out the average output signal e. are doing. Then, the gain calculation unit 12 divides the local neutron flux average signal k by the average output signal e to obtain the local neutron flux average gain k / e, and the gain multiplication unit 13 then determines the gain k / e.
Upon receiving / e, the local neutron flux average signal k is multiplied, and the multiplied value is sent to the trip determination unit 15 as a local output r.
一方、流量変換器16は原子炉へ供給される一次冷却水
の流量を検出してその流量検出信号を出力している。ト
リップレベル算出部14はこの流量検出信号を受けて流量
に応じたトリップレベルtpに変換してトリップ判定部15
に送出する。かくして、このトリップ判定部15は局部出
力ｒとトリップレベルtpとを比較して、例えば局部出力
ｒのレベルがトリップレベルtp以上となれば制御棒引抜
き阻止信号Ｗを原子炉手動制御装置10へ送出する。この
結果、制御棒３の引抜きは停止される。On the other hand, the flow rate converter 16 detects the flow rate of the primary cooling water supplied to the nuclear reactor and outputs the flow rate detection signal. The trip level calculation unit 14 receives the flow rate detection signal and converts it into a trip level tp corresponding to the flow rate, and the trip determination unit 15
Send to. Thus, the trip determination unit 15 compares the local output r with the trip level tp, and if the level of the local output r is equal to or higher than the trip level tp, sends the control rod withdrawal prevention signal W to the reactor manual control device 10. To do. As a result, the withdrawal of the control rod 3 is stopped.
このように上記一実施例においては、制御棒２が引抜
かれるとこの制御棒２を囲む如く配置された各中性子束
検出器３からの中性子束検出信号を選択し，これら選択
された中性子束検出信号に対して距離の比重を乗算して
各中性子束検出信号の平均値を求め、この求められた局
部中性子束平均値に基づいて局部出力の上昇を判定する
ので、制御棒２の引抜きによる影響の大きい中性子束検
出器の出力に対して相対的に増加させるとともに制御棒
２の引抜きによる影響の少ない中性子束検出器の出力に
対して相対的に減衰させて、制御棒２が引抜かれたとき
の局部出力上昇を顕著に示すことができる。従って、局
部出力上昇を正確に監視できる。Thus, in the above-described embodiment, when the control rod 2 is pulled out, the neutron flux detection signals from the neutron flux detectors 3 arranged so as to surround the control rod 2 are selected, and the selected neutron flux detection is performed. The signal is multiplied by the specific gravity of the distance to obtain the average value of each neutron flux detection signal, and the increase in the local output is determined based on the obtained average value of the local neutron flux. When the control rod 2 is withdrawn, the output is relatively increased with respect to the output of the neutron flux detector, and the output is relatively attenuated with respect to the output of the neutron flux detector, which is less affected by the withdrawal of the control rod 2. It is possible to show a marked increase in local output of. Therefore, the local output increase can be accurately monitored.
なお、本発明は上記一実施例に限定されるものでなく
その主旨を逸脱しない範囲で変形してもよい。例えば、
上記一実施例では各中性子束検出信号に対して距離の比
重を乗算して局部中性子束平均信号を求めているが、距
離の比重に変えて核的距離（ミンフリーパス）の逆数や
立体角に反比例する値、さらにこれら値に各中性子束検
出器の効率に影響する物理量，制御棒に対する中性子束
検出器の感度等やこれら値を複数組合わせた値にしても
よい。It should be noted that the present invention is not limited to the above-described embodiment, and may be modified without departing from the spirit of the invention. For example,
In the above-mentioned one embodiment, each neutron flux detection signal is multiplied by the specific gravity of the distance to obtain the local neutron flux average signal. May be a value that is inversely proportional to, a physical quantity that affects the efficiency of each neutron flux detector, a sensitivity of the neutron flux detector with respect to the control rod, or a value obtained by combining a plurality of these values.
［発明の効果］ 以上詳記したように本発明によれば、制御棒引抜きに
よる局部出力上昇を正確に監視できる制御棒引抜き監視
装置を提供できる。[Effects of the Invention] As described in detail above, according to the present invention, it is possible to provide a control rod withdrawal monitoring device capable of accurately monitoring a local output increase due to control rod withdrawal.
第１図及び第２図は本発明に係わる制御棒引抜き監視装
置の一実施例を説明するための図であって、第１図は全
体構成図、第２図は局部中性子束平均値を算出を説明す
るための模式図、第３図は沸騰水型原子炉の断面図、第
４図は中性子束検出器の外観図である。 １……燃料棒、２……制御棒、３……中性子束検出器、
６−１〜６−ｎ……局部出力モニタ、７……平均出力モ
ニタ、８……制御棒引抜き監視装置、９……局部出力選
択算出部、10……原子炉手動制御装置、11……局部出力
判定手段、12……利得算出部、13……利得乗算部、14…
…トリップレベル算出部、15……トリップ判定部、16…
…流量変換器。1 and 2 are views for explaining an embodiment of a control rod pull-out monitoring device according to the present invention, in which FIG. 1 is an overall configuration diagram, and FIG. 2 is calculation of a local neutron flux average value. FIG. 3 is a cross-sectional view of a boiling water reactor, and FIG. 4 is an external view of a neutron flux detector. 1 ... Fuel rod, 2 ... Control rod, 3 ... Neutron flux detector,
6-1 to 6-n ... Local output monitor, 7 ... Average output monitor, 8 ... Control rod withdrawal monitoring device, 9 ... Local output selection calculation unit, 10 ... Reactor manual control device, 11 ... Local output determination means, 12 ... Gain calculation section, 13 ... Gain multiplication section, 14 ...
… Trip level calculation unit, 15 …… Trip determination unit, 16…
… Flow rate converter.
Claims (1)
体の間に規則的に配置された制御棒を引抜いたときに生
じる局部的な出力上昇を前記原子炉炉心内に配置された
各中性子束検出器からの中性子束検出信号を受けて監視
する制御棒引抜き監視装置において、引抜かれる前記制
御棒を囲む如く配置された前記各中性子束検出器からの
中性子束検出信号を選択して取込み，これら中性子束検
出信号に対して選択された前記各中性子束検出器への前
記制御棒の引抜きによる中性子束の影響度を加えて前記
各中性子束検出信号の平均値を求める局部平均算出手段
と、この局部平均算出手段で求められた局部中性子束平
均値に基づいて局部出力上昇の判定を行う局部出力判定
手段とを具備したことを特徴とする制御棒引抜き監視装
置。1. A local power increase which occurs when a control rod regularly arranged between a plurality of fuel assemblies arranged in a reactor core is pulled out is arranged in the reactor core. In the control rod withdrawal monitoring device for receiving and monitoring the neutron flux detection signal from each neutron flux detector, by selecting the neutron flux detection signal from each neutron flux detector arranged to surround the control rod to be withdrawn A local average calculating means for obtaining the average value of each neutron flux detection signal by adding the influence degree of the neutron flux due to the pulling of the control rod to each neutron flux detector selected for these neutron flux detection signals And a local output determining means for determining a local output increase based on the local neutron flux average value obtained by the local average calculating means.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63039585A JPH0830749B2 (en) | 1988-02-24 | 1988-02-24 | Control rod withdrawal monitoring device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63039585A JPH0830749B2 (en) | 1988-02-24 | 1988-02-24 | Control rod withdrawal monitoring device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01214794A JPH01214794A (en) | 1989-08-29 |
| JPH0830749B2 true JPH0830749B2 (en) | 1996-03-27 |
Family
ID=12557173
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63039585A Expired - Fee Related JPH0830749B2 (en) | 1988-02-24 | 1988-02-24 | Control rod withdrawal monitoring device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0830749B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106782686B (en) * | 2015-11-20 | 2023-11-21 | 国核（北京）科学技术研究院有限公司 | Method for arranging detectors of core loaded with 185-cartridge fuel assemblies and core thereof |
| JP6453262B2 (en) * | 2016-03-09 | 2019-01-16 | 日立Ｇｅニュークリア・エナジー株式会社 | Control rod operation monitoring method and control rod operation monitoring system |
-
1988
- 1988-02-24 JP JP63039585A patent/JPH0830749B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH01214794A (en) | 1989-08-29 |
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