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JPS6346396B2 - - Google Patents
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JPS6346396B2 - - Google Patents

Info

Publication number
JPS6346396B2
JPS6346396B2 JP55037209A JP3720980A JPS6346396B2 JP S6346396 B2 JPS6346396 B2 JP S6346396B2 JP 55037209 A JP55037209 A JP 55037209A JP 3720980 A JP3720980 A JP 3720980A JP S6346396 B2 JPS6346396 B2 JP S6346396B2
Authority
JP
Japan
Prior art keywords
core
reactor
water level
neutron
insulation resistance
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
Application number
JP55037209A
Other languages
Japanese (ja)
Other versions
JPS56133693A (en
Inventor
Tomio Tsunoda
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Toshiba Corp, Nippon Genshiryoku Jigyo KK filed Critical Toshiba Corp
Priority to JP3720980A priority Critical patent/JPS56133693A/en
Publication of JPS56133693A publication Critical patent/JPS56133693A/en
Publication of JPS6346396B2 publication Critical patent/JPS6346396B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は原子炉水位が低下して炉心が露出した
場合、これを直ちに検出して警報を発生する原子
炉の炉心露出監視装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a reactor core exposure monitoring system that immediately detects and issues an alarm when the reactor core is exposed due to a drop in the reactor water level.

原子炉発電所では、通常、炉心内に多数の中性
子検出器を設置し、炉内各部における局部的な中
性子密度を測定している。
In nuclear power plants, a large number of neutron detectors are usually installed in the reactor core to measure local neutron density in various parts of the reactor.

例えば、沸騰水形原子炉には多数の局所出力領
域モニタ、中間領域モニタ、中性子源モニタおよ
び移動型中性子検出器が配置され、炉心制御に使
用されている。
For example, a boiling water reactor is equipped with a large number of local power range monitors, intermediate range monitors, neutron source monitors, and mobile neutron detectors, which are used for core control.

事故発生時に原子炉内の水位が一定レベル以下
に低下すると原子炉保護系が作動して原子炉制御
棒が全挿入され、原子炉は緊急停止して炉心内の
中性子束レベルは急激に低下する。
When the water level inside the reactor drops below a certain level in the event of an accident, the reactor protection system is activated, the reactor control rods are fully inserted, the reactor is brought to an emergency shutdown, and the neutron flux level within the reactor core drops rapidly. .

原子炉水位が更に下降した場合でも、原子炉水
位計が正常に動作しておれば、これを監視するこ
とにより緊急注水系の作動等により炉心の露出を
防止することができるのであるが、水位計が正常
に動作しない場合には、炉内水位を正確に把握す
ることができず、適切な対応策が遅れて二次災害
を紹来する危険がある。
Even if the reactor water level drops further, as long as the reactor water level gauge is operating normally, by monitoring this it is possible to prevent the core from being exposed by activating the emergency water injection system, etc. If the gauge does not operate normally, the water level inside the reactor cannot be accurately determined, and there is a risk that appropriate countermeasures will be delayed, leading to secondary disasters.

通常運転中の炉内冷却水の温度は炉形によつて
異なるが、280℃〜320℃程度であり、従つて、冷
却水位が正常であれば、これ以上の温度にはなら
ない。
The temperature of the cooling water in the furnace during normal operation varies depending on the furnace type, but is approximately 280°C to 320°C, and therefore, if the cooling water level is normal, the temperature will not exceed this temperature.

しかしながら、何等かの原因により、冷却水の
水位が低下して炉心が露出すると、制御棒が全挿
入されていたとしても、熱除去が不十分になるた
め、炉心内の温度は400℃を越えることになる。
However, if for some reason the cooling water level drops and the core is exposed, even if the control rods are fully inserted, heat removal will not be sufficient and the temperature inside the core will exceed 400℃. It turns out.

従つて、炉心内の温度を測定監視すれば炉心の
露出を監視することができる。
Therefore, by measuring and monitoring the temperature within the core, exposure of the core can be monitored.

ところで、前述の中性子検出器の出力は夫々リ
ード線を介して原子炉容器から引出され、測定装
置に導かれるが、これらのリード線は優れた耐熱
性を要するところから、通常、無機絶縁電線が使
用される。
By the way, the output of the neutron detectors mentioned above is drawn out from the reactor vessel through lead wires and guided to the measuring device, but these lead wires require excellent heat resistance, so inorganic insulated wires are usually used. used.

この電線は線間の絶縁抵抗が温度によつて大巾
に変化するという性質がある。
This electric wire has the property that the insulation resistance between the wires changes greatly depending on the temperature.

本発明はかかる点に着目してなされたもので、
中性子検出器およびそのリード線の絶縁抵抗を測
定監視することによつて炉内温度ひいては炉心の
露出を監視しようとするものである。
The present invention has been made with attention to this point,
By measuring and monitoring the insulation resistance of the neutron detector and its lead wires, it is intended to monitor the temperature inside the reactor and thus the exposure of the reactor core.

以下、図示の実施例につき、本発明の詳細を説
明する。
The present invention will be explained in detail below with reference to the illustrated embodiments.

第1図は沸騰水形原子力発電所における炉内中
性子検出器の装荷状態を概念的に示すもので、移
動型の中性子検出器S1は炉心1の上端位置に載置
され、また局所出力領域モニタとしての中性子検
出器72〜S5は縦方向に適当間隔をおいて順次設
置されている。
Figure 1 conceptually shows the loading state of in-core neutron detectors in a boiling water nuclear power plant. A mobile neutron detector S1 is placed at the upper end of the reactor core 1, and Neutron detectors 7 2 to S 5 as monitors are sequentially installed at appropriate intervals in the vertical direction.

これらの中性子検出器は夫々リード線2を介し
て局所出力領域モニタ増巾器3に接続される共に
切換スイツチSwを介して絶縁測定器4に接続さ
れている。
These neutron detectors are each connected to a local power range monitor amplifier 3 via a lead wire 2, and to an insulation measuring device 4 via a changeover switch Sw.

この絶縁測定器の出力は警報回路5において、
基準値と比較され、それが基準値以下となつた場
合には警報器6を作動させる。
The output of this insulation measuring device is sent to the alarm circuit 5.
It is compared with a reference value, and if it is less than the reference value, the alarm 6 is activated.

上記において、リード線2はいずれも無機絶縁
電線をもつて構成されている。
In the above, the lead wires 2 are all made of inorganic insulated wires.

この電線は銅管やステンレス管から成るシース
内にマグネシヤやアルミナ絶縁材料を介して1本
または複数本の芯線を配列したものである。
This electric wire has one or more core wires arranged within a sheath made of a copper tube or stainless steel tube with an insulating material of magnesia or alumina interposed therebetween.

この無機絶縁電線の芯線間または芯線・シース
間の絶縁抵抗値は周囲温度の変化に伴い大巾に変
化する。
The insulation resistance value between the core wires or between the core wire and the sheath of this inorganic insulated wire changes widely with changes in ambient temperature.

即ち、第2図に例示するように、300℃におけ
る絶縁抵抗は9×1010Ω程度であるが、400℃に
なるとこれが1.5×109Ω程度となり、約1/40に低
下する。
That is, as illustrated in FIG. 2, the insulation resistance at 300° C. is about 9×10 10 Ω, but at 400° C., this becomes about 1.5×10 9 Ω, which is reduced to about 1/40.

従つて、第3図に示すように中性子検出器Sに
接続した無機絶縁電線2の他端側の芯線2aとシ
ース2b間に抵抗Rを介して電源Eを接続し、抵
抗Rの端子間電圧Vを電圧計Vmで測定すれば、
中性子検出器Sおよび無機絶縁電線2の抵抗rは
次式から求められる。
Therefore, as shown in FIG. 3, a power source E is connected via a resistor R between the core wire 2a and sheath 2b at the other end of the inorganic insulated wire 2 connected to the neutron detector S, and the voltage between the terminals of the resistor R is If you measure V with a voltmeter Vm,
The resistance r of the neutron detector S and the inorganic insulated wire 2 is calculated from the following equation.

r=R(E/V−1) 炉心の水位が第4図Aに示すように変化する場
合、水位が炉心上端に達する以前には中性子検出
器S1〜S5とそれらのリード線の絶縁抵抗はいずれ
も同図Bに示すように6×1010Ω程度であるが、
時間t1において水位が炉心上端より低下すると中
性子検出器S1とそのリード線の絶縁抵抗は同図B
のように急激に低下する。
r=R(E/V-1) When the water level in the core changes as shown in Figure 4A, the insulation of neutron detectors S1 to S5 and their lead wires must be removed before the water level reaches the top of the core. The resistance in each case is about 6× 10 Ω, as shown in Figure B.
When the water level falls below the top of the core at time t 1 , the insulation resistance of the neutron detector S 1 and its lead wire will change to B in the same figure.
decreases rapidly.

更に水位が低下して時間t2において、レベルA
(第1図参照)に達すると中性子検出器S2および
そのリード線の絶縁抵抗が同図Bのように低下す
る。
The water level further decreases to level A at time t2 .
(See Figure 1), the insulation resistance of the neutron detector S2 and its lead wires decreases as shown in Figure B.

このように本発明装置においては、炉心水位の
低下を中性子検出器のリード線の絶縁抵抗値の変
化に基づいて測定監視することができるので、炉
心が露出した場合には直ちに警報が発せられ、緊
急注水系の作動その他の対策を講ずることができ
る。
In this way, in the device of the present invention, the drop in the core water level can be measured and monitored based on the change in the insulation resistance value of the lead wire of the neutron detector, so if the core is exposed, an alarm is immediately issued. It is possible to activate the emergency water injection system and take other measures.

なお、図示の例では中性子検出器を5個だけ示
したが、実際の原子炉では20〜150個の中性子検
出器が配置されているのでそれらの設置高さを異
ならせておけば、炉心水位レベルを細かなレンジ
で判別することができる。
Although the illustrated example shows only five neutron detectors, in an actual nuclear reactor, 20 to 150 neutron detectors are arranged, so if they are installed at different heights, the core water level can be adjusted. Levels can be determined in fine ranges.

なお、本発明では中性子検出器と局部出力領域
モニタ増巾器の間を連結するリード線を水位レベ
ルの検出に共用するものであるが、中性子の検量
は主として原子炉の通常運転中に行なわれるに対
して水位レベルの検出は原子炉の停止時に行なわ
れるので、上記共用による不都合はない。
In addition, in the present invention, the lead wire connecting the neutron detector and the local power range monitor amplifier is commonly used for water level detection, but neutron calibration is mainly performed during normal operation of the reactor. On the other hand, since water level detection is performed when the reactor is shut down, there is no inconvenience due to the above-mentioned common use.

もつとも中性子の検量と水位レベルを併行して
行ないたい場合には公知の時分割方式の導入によ
り容易に実現することができる。
However, if it is desired to perform neutron calibration and water level measurement simultaneously, this can be easily achieved by introducing a known time division method.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は原子炉内に設置した中性子検出器とそ
の付属回路の関係を概念的に示す回路図、第2図
は本発明において使用される無機絶縁電線の周囲
温度と絶縁抵抗の関係を示すグラフ、第3図は本
発明における絶縁抵抗の測定原理を説明する回路
図、第4図は炉心水位と絶縁抵抗の変化の関係を
示すグラフである。 1…炉心、2…リード線(無機絶縁電線)、2
a…芯線、2b…シース、S,S1〜S5…中性子検
出器。
Figure 1 is a circuit diagram conceptually showing the relationship between a neutron detector installed in a nuclear reactor and its attached circuit, and Figure 2 shows the relationship between ambient temperature and insulation resistance of the inorganic insulated wire used in the present invention. FIG. 3 is a circuit diagram explaining the principle of measuring insulation resistance in the present invention, and FIG. 4 is a graph showing the relationship between core water level and change in insulation resistance. 1...Reactor core, 2...Lead wire (inorganic insulated wire), 2
a...core wire, 2b...sheath, S, S1 to S5 ...neutron detector.

Claims (1)

【特許請求の範囲】 1 原子炉炉心に挿入した中性子検出器およびそ
のリード線の絶縁抵抗を測定し、これと予め定め
た基準値と比較して測定値が基準値以下になつた
際に警報を発するように構成したことを特徴とす
る原子炉の炉心露出監視装置。 2 リード線は無機絶縁電線から成ることを特徴
とする特許請求の範囲第1項記載の原子炉の炉心
露出監視装置。
[Claims] 1. Measures the insulation resistance of a neutron detector inserted into the reactor core and its lead wires, compares this with a predetermined reference value, and issues an alarm when the measured value falls below the reference value. A nuclear reactor core exposure monitoring device characterized in that it is configured to emit. 2. The reactor core exposure monitoring device according to claim 1, wherein the lead wire is made of an inorganic insulated wire.
JP3720980A 1980-03-24 1980-03-24 Reactor core exposure monitoring device Granted JPS56133693A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3720980A JPS56133693A (en) 1980-03-24 1980-03-24 Reactor core exposure monitoring device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3720980A JPS56133693A (en) 1980-03-24 1980-03-24 Reactor core exposure monitoring device

Publications (2)

Publication Number Publication Date
JPS56133693A JPS56133693A (en) 1981-10-19
JPS6346396B2 true JPS6346396B2 (en) 1988-09-14

Family

ID=12491196

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3720980A Granted JPS56133693A (en) 1980-03-24 1980-03-24 Reactor core exposure monitoring device

Country Status (1)

Country Link
JP (1) JPS56133693A (en)

Also Published As

Publication number Publication date
JPS56133693A (en) 1981-10-19

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