JPS60200196A - Control-rod drawing monitor device - Google Patents
Control-rod drawing monitor deviceInfo
- Publication number
- JPS60200196A JPS60200196A JP59056083A JP5608384A JPS60200196A JP S60200196 A JPS60200196 A JP S60200196A JP 59056083 A JP59056083 A JP 59056083A JP 5608384 A JP5608384 A JP 5608384A JP S60200196 A JPS60200196 A JP S60200196A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- neutron flux
- signal
- withdrawal
- control
- 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
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】
〔発明の利用分野〕
本発明は軽水型原子炉の安全設備に係り、特に原子炉に
おける制御棒引抜監視装置に関するものであり、制御棒
落下事故を防止し、原子炉の安全性、信頼性向上を図る
ことを目的としたものである。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to safety equipment for light water nuclear reactors, and in particular to a control rod withdrawal monitoring device in a nuclear reactor, which prevents control rod fall accidents and improves the safety of nuclear reactors. The purpose is to improve the safety and reliability of the system.
原子炉の安全性を確認するために考慮すべき項目の１つ
に制御棒落下事故がある。これは、制御棒が落下した場
合、この落下制御棒により即発中性子のみで臨界に達す
る程度に大きな正の核的反応度が投入される（即発臨界
条件に達する）と第１図に示す如く、ごく短時間に非常
に大きな炉心出力の上昇を引き起こし、炉心にダメージ
を与えるためである。One of the items that must be considered to confirm the safety of a nuclear reactor is a control rod fall accident. This means that when a control rod falls, a large positive nuclear reactivity is injected by the falling control rod to the extent that it reaches criticality with only prompt neutrons (the prompt critical condition is reached), as shown in Figure 1. This is because it causes a very large increase in core power in a very short period of time, causing damage to the reactor core.
この制御棒落下は次に示すような仮想的な場合に生ずる
。即ち、制御棒を炉心から引抜こうとした時、何らかの
原因で制御棒が燃料チャンネルボックス等にひっかかり
、制御棒駆動装置との接続部がはずれ、制御棒駆動部の
み引抜かれた状態となる。その後さらに何らかの原因で
制御棒がはずれ制御棒が落下すると仮定する。This control rod fall would occur in the following hypothetical case. That is, when attempting to pull out the control rods from the reactor core, the control rods get caught in a fuel channel box or the like for some reason, and the connection to the control rod drive device becomes disconnected, leaving only the control rod drive section to be pulled out. It is assumed that the control rod subsequently detaches for some reason and falls.
従来ではこの制御棒と制御棒駆動装置が接続されている
ことを監視する手段がないため制御捧落下が生ずると仮
定し、制御棒落下事故を緩和するり′、″：二二二：：
Ｉｌ：、；ル。、８．。。１ｉｄｊｌ＆：＃いて、制御
棒落下による投入反応度が所期の値以下になるような運
転手順を定め、この運転手順に従って制御棒が引抜かれ
るよう監視するプログラム（ＲＷＭ）をプロセス計算機
に内蔵して監視する等の対策がとられていた。しかしい
ずれにせよ制御棒落下を防止するというより、落下が生
じた時のダメージを緩和する対策であり、落下そのもの
を防止するものではなかった。Conventionally, there was no means to monitor whether the control rod and the control rod drive device were connected, so it was assumed that the control rod would fall, and the control rod fall accident could be mitigated.
Il:, ;le. , 8. . . 1idjl &:# The process computer has a built-in program (RWM) that establishes an operating procedure to ensure that the input reactivity due to a control rod falling is below the desired value, and monitors that the control rod is withdrawn according to this operating procedure. Measures such as monitoring were taken. However, in any case, rather than preventing the control rod from falling, it was a measure to alleviate the damage that would occur if a control rod were to fall, and not to prevent the rod from falling itself.
本発明は、前述のような従来型原炉に対して。 The present invention is directed to the conventional nuclear reactor as described above.
制御棒が制御棒駆動装置に連結されていることを監視す
る装置を設け、制御棒の引抜きに対する信頼性を増大さ
せ、原子炉の安全性を向上させるものである。A device is provided to monitor whether the control rods are connected to the control rod drive device, thereby increasing the reliability of control rod withdrawal and improving the safety of the nuclear reactor.
運転中の原子炉において、制御棒操作信号と中性子束信
号の変化量を用いて、制御棒操作時に中性子束が正常に
変化（制御棒引抜きの場合は、中性子束が増加、制御棒
挿入の場合は中性子束が減少）することを判断し、中性
子束の変化が異常な場合は制御棒の操作を阻止または警
報を発する機能を備えた装置である。In an operating nuclear reactor, the amount of change in the control rod operation signal and neutron flux signal is used to determine whether the neutron flux changes normally during control rod operation (in the case of control rod withdrawal, the neutron flux increases, and in the case of control rod insertion) This device has the function of determining whether the neutron flux is decreasing) and preventing control rod operation or issuing an alarm if the change in neutron flux is abnormal.
以下１本発明の実施例を図面に基づいて詳細に説明する
。第２図は、沸騰水型原子炉の炉心部分側面図を示す。EMBODIMENT OF THE INVENTION Below, one embodiment of the present invention will be described in detail based on the drawings. FIG. 2 shows a side view of a portion of the core of a boiling water reactor.
図において制御棒（２）は運転中炉心内部（７）に適当
に挿入され、出力分布および反応度制御を行う。制御棒
（２）は炉心停止時は全数炉心内に挿入されている。原
子炉を起動し、定格出力で定常運転するには、制御棒を
順次炉心引き抜いていく。In the figure, control rods (2) are appropriately inserted into the reactor core (7) during operation to control power distribution and reactivity. All control rods (2) are inserted into the reactor core when the reactor core is stopped. To start up a nuclear reactor and maintain steady operation at rated power, the control rods are sequentially pulled out of the core.
第３図に本発明による制御棒引抜き監視装置の構成を示
す。原子炉（１）内の測定された計測信号は、プロセス
入力処理装置（５）を介して、記憶される。本発明はこ
のプロセス入力処理装置および本発明で新たに追加され
る監視装置（６）で構成される。FIG. 3 shows the configuration of a control rod withdrawal monitoring device according to the present invention. The measured measurement signals in the nuclear reactor (1) are stored via a process input processing device (5). The present invention is comprised of this process input processing device and a monitoring device (6) newly added in the present invention.
監視装置の詳細を第４図に示す。この監視装置では、制
御棒操作信号を基に、制御棒が引抜かれたかどうかを判
定する。引抜きの場合は、中性子束変化信号を基に、中
性子束が上昇したかどうかを判定し、上昇の場合は、制
御棒の引抜きが正常であり、通常の監視に戻る。Details of the monitoring device are shown in FIG. This monitoring device determines whether a control rod has been pulled out based on a control rod operation signal. In the case of withdrawal, it is determined whether the neutron flux has increased based on the neutron flux change signal, and if it has increased, the withdrawal of the control rod is normal and normal monitoring is resumed.
また、制御棒を引抜いたが中性子束が上昇しない場合は
、なんらかの原因でその周囲（チャンネルボックス）と
固くくっついて（ステック）いて、駆動軸のみが引抜か
れて、制御棒本体は炉心内にとどまりたと考えられるの
で、この場合は、制御棒に引抜阻止信号（ブロック信号
）を発生させ、インターロック（４）によりその後の制
御棒引抜き操作は、阻止され、さらに警報を発生させる
。Also, if the neutron flux does not rise even after the control rod is pulled out, it may be stuck to the surrounding area (channel box) for some reason, and only the drive shaft is pulled out, and the control rod body remains in the reactor core. Therefore, in this case, a withdrawal prevention signal (block signal) is generated for the control rod, and the subsequent control rod withdrawal operation is blocked by the interlock (4), and an alarm is also generated.
この警報に基づき、運転員が対策をとり、制御棒駆動系
が正常に復帰した場合は制御棒引抜阻止信号を解除し次
の操作に移る。一方、制御棒を挿入した場合は、中性子
束信号が、下降したかどうかを判定し、下降であれば通
常の監視に戻る。また制御棒を挿入したが中性子束が下
降しない場合は。Based on this warning, the operator takes countermeasures, and when the control rod drive system returns to normal, the control rod withdrawal prevention signal is canceled and the next operation is started. On the other hand, if a control rod is inserted, the neutron flux signal determines whether it has descended, and if so, returns to normal monitoring. Also, if the control rod is inserted but the neutron flux does not descend.
なんらかの異常があるものとして警報を発生させる。制
御棒挿入の場合は原子炉を停止させようとする安全側の
操作であるので、制御棒操作のブロックは不必要である
。An alarm is generated assuming that there is some kind of abnormality. In the case of control rod insertion, it is a safe operation to stop the reactor, so a control rod operation block is unnecessary.
本発明に基づく制御棒引抜監視装置を設置した場合は制
御棒は制御棒駆動軸と確実に接続されていることが確認
されているので制御棒落下事故は生じない。When the control rod withdrawal monitoring device according to the present invention is installed, it is confirmed that the control rods are securely connected to the control rod drive shaft, so no control rod fall accidents occur.
変監叢
沸騰水型原子炉の炉心を第５図に示す、第５図で１１は
中性子検出ストリング、１２は制御棒であり、中性子検
出ストリング１１は、制御棒１２を取り囲むように配置
されている。中性子検出ストリング１１と、制御棒１２
の相対関係を示す概念図を第６図に示す。第６図の中性
子束信号および制御棒位置信号は制御棒引抜監視装置に
送られる。第７図に制御棒引抜監視装置を示す。第７図
で、ある制御棒が引抜くために選択されると、この信号
は制御棒選択検出回路１４．中性子検出ストリング選択
回路１５に送られ、各回路において選択された制御棒位
置信号は記憶・比較回路１７に送られ、この制御棒を囲
む４本の中性子検出ストリング信号は加算回路１６に送
られる。加算回路１６で合計された中性子束信号は記憶
・比較回路１７に送られる。記憶比較回路１７において
、制御棒位置信号に基づき、制御棒が引抜かれたか挿入
されたか判断される。The core of the boiling water reactor is shown in FIG. 5. In FIG. 5, 11 is a neutron detection string, and 12 is a control rod. There is. Neutron detection string 11 and control rod 12
A conceptual diagram showing the relative relationship between the two is shown in FIG. The neutron flux signal and control rod position signal in FIG. 6 are sent to a control rod withdrawal monitoring device. Figure 7 shows the control rod withdrawal monitoring device. In FIG. 7, when a control rod is selected for withdrawal, this signal is transmitted to the control rod selection detection circuit 14. The control rod position signals sent to the neutron detection string selection circuit 15 and selected in each circuit are sent to the storage/comparison circuit 17, and the four neutron detection string signals surrounding this control rod are sent to the addition circuit 16. The neutron flux signals summed by the adder circuit 16 are sent to the storage/comparison circuit 17. In the memory comparison circuit 17, it is determined based on the control rod position signal whether the control rod is withdrawn or inserted.
記憶・比較回路の詳細を第８図に示す。第８図において
制御棒引抜きの場合は、引抜後の中性子束合計信号が、
引抜前の中性子束合計信号より大きければ（上昇した場
合は）正常であり、通常の監視に戻る。Details of the storage/comparison circuit are shown in FIG. In Fig. 8, in the case of control rod withdrawal, the neutron flux total signal after withdrawal is
If it is larger than the neutron flux total signal before extraction (if it rises), it is normal, and normal monitoring returns.
また、制御棒を引抜いたが中性子束合計値が増加しない
場合は、なんらかの原因でその周囲（チャンネルボック
ス）と固くくっついて（ステック）いて駆動軸のみが引
抜かれて、制御棒本体は、炉心内にとどまったと考えら
れるので、この場合は制御棒に引抜阻止信号（ブロック
信号）を発生させインターロック（４）によりその後に
の制御棒引抜き操作は、阻止され、さらに警報を発生さ
せる。この警報に基づき、運転員が対策をとり制御棒駆
動系が正常に復帰した場合は制御棒引抜阻止信号を解除
し次の操作に移る。In addition, if the total neutron flux does not increase even after the control rod is pulled out, the control rod body is stuck inside the reactor core due to some reason that it is firmly stuck to its surroundings (channel box) and only the drive shaft is pulled out. In this case, a withdrawal prevention signal (block signal) is generated for the control rod, and the interlock (4) prevents the control rod from being withdrawn thereafter, and an alarm is also generated. Based on this warning, the operator takes countermeasures, and if the control rod drive system returns to normal, the control rod withdrawal prevention signal is canceled and the next operation is started.
一方、制御棒を挿入した場合は、中性子束合計信号が下
降したかどうかを判定し、下降であれば、通常の監視に
戻る。また制御棒を挿入したが中性子束が下降しない場
合は、なんらかの異常があるものとして、警報を発生さ
せる。On the other hand, when a control rod is inserted, it is determined whether the total neutron flux signal has decreased, and if it has decreased, normal monitoring is resumed. Furthermore, if the neutron flux does not descend even after the control rod is inserted, it is assumed that there is some abnormality and an alarm is generated.
制御棒挿入の場合は、原子炉を停止させようとする安全
側の操作であるので、制御棒操作のブロックは、不必要
である。In the case of control rod insertion, the control rod operation block is unnecessary because it is a safe operation that attempts to stop the reactor.
本発明に基づく制御棒引抜監視装置を設置した場合は制
御棒は制御棒駆動軸と確実に接続されていることが確認
されているので制御棒落下事故は生じない。When the control rod withdrawal monitoring device according to the present invention is installed, it is confirmed that the control rods are securely connected to the control rod drive shaft, so no control rod fall accidents occur.
本発明により、制御棒は制御棒駆動軸に確実に接続され
ていることが監視されているので、制御棒落下事故を未
然に防止できる。According to the present invention, since it is monitored that the control rod is reliably connected to the control rod drive shaft, it is possible to prevent a control rod falling accident.
第１図は制御棒落下事故時の炉内出力変化図、第２図は
沸騰水型原子炉の炉心側面図、第３図は本発明による制
御棒引抜監視装置構成図、第４図は本発明による制御棒
引抜監視装置詳細図、第５図は原子炉配置図、第６図は
制御棒、中性子検出ストリング配置図、第７図は制御棒
引抜監視装置の変形例を示す図、第８図は記憶・比較回
路詳細図である。
１・・・原子炉、２・・制御棒、３・・・制御棒駆動機
構、４・・・インターロック、５・・入力取込装置、６
・・・監視装置、７ ・原子炉内部、１１・・・制御棒
、１２・・中性子検出器ストリング、１４・・制御棒選
択検出回路、１５・・・中性子検出ストリンク選択回路
、１６・・・加算回路、１７・・・記憶比較回路。
代理人 弁理士 高橋明夫
第３図Figure 1 is a diagram of the power output change in the reactor during a control rod fall accident, Figure 2 is a side view of the core of a boiling water reactor, Figure 3 is a configuration diagram of the control rod withdrawal monitoring device according to the present invention, and Figure 4 is a diagram of the present invention. A detailed view of the control rod withdrawal monitoring device according to the invention, FIG. 5 is a reactor layout diagram, FIG. 6 is a control rod and neutron detection string layout diagram, FIG. 7 is a diagram showing a modification of the control rod withdrawal monitoring device, and FIG. 8 The figure is a detailed diagram of the storage/comparison circuit. DESCRIPTION OF SYMBOLS 1... Nuclear reactor, 2... Control rod, 3... Control rod drive mechanism, 4... Interlock, 5... Input acquisition device, 6
...Monitoring device, 7. Reactor interior, 11.. Control rod, 12.. Neutron detector string, 14.. Control rod selection detection circuit, 15.. Neutron detection string selection circuit, 16.. - Addition circuit, 17... memory comparison circuit. Agent Patent Attorney Akio Takahashi Figure 3
Claims (1)
信号を検出し前記制御棒信号により制御棒の操作を判定
し制御棒が引抜かれたと判定された時前記中性子東信号
が上昇するか否かを判定し中性子束が上昇しない場合は
解除信号が入力されるまで判定された時点以降の制御棒
引抜を阻止することを特徴とした制御棒引抜監視装置。 ２、特許請求の範囲第１項において、中性子束信号とし
て制御棒を囲む４つの中性子束検出ストリングの信月の
合計値を用いこの合計値の制御棒引抜前後における大小
関係により中性子束の上昇を判定することを特徴とする
制御棒引抜監視装置。[Scope of Claims] (1) In a light water reactor, when a control rod operation signal and a neutron flux signal are detected, the operation of the control rod is determined based on the control rod signal, and it is determined that the control rod has been pulled out, the neutron flux A control rod withdrawal monitoring device that determines whether or not a signal increases, and if the neutron flux does not increase, prevents control rod withdrawal after the determined time until a release signal is input. 2. In claim 1, the total value of the four neutron flux detection strings surrounding the control rod is used as the neutron flux signal, and the increase in neutron flux is determined by the magnitude relationship of this total value before and after the control rod is withdrawn. A control rod withdrawal monitoring device characterized by making a determination.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59056083A JPS60200196A (en) | 1984-03-26 | 1984-03-26 | Control-rod drawing monitor device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59056083A JPS60200196A (en) | 1984-03-26 | 1984-03-26 | Control-rod drawing monitor device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS60200196A true JPS60200196A (en) | 1985-10-09 |
Family
ID=13017189
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59056083A Pending JPS60200196A (en) | 1984-03-26 | 1984-03-26 | Control-rod drawing monitor device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60200196A (en) |
-
1984
- 1984-03-26 JP JP59056083A patent/JPS60200196A/en active Pending
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