JP3893563B2 - Control rod position display device - Google Patents

Control rod position display device Download PDF

Info

Publication number
JP3893563B2
JP3893563B2 JP2003048880A JP2003048880A JP3893563B2 JP 3893563 B2 JP3893563 B2 JP 3893563B2 JP 2003048880 A JP2003048880 A JP 2003048880A JP 2003048880 A JP2003048880 A JP 2003048880A JP 3893563 B2 JP3893563 B2 JP 3893563B2
Authority
JP
Japan
Prior art keywords
control rod
rod position
signal
control
position detection
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
Application number
JP2003048880A
Other languages
Japanese (ja)
Other versions
JP2004257863A (en
Inventor
健 野崎
好美 後藤
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP2003048880A priority Critical patent/JP3893563B2/en
Publication of JP2004257863A publication Critical patent/JP2004257863A/en
Application granted granted Critical
Publication of JP3893563B2 publication Critical patent/JP3893563B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Images

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

【０００１】
【発明の属する技術分野】
本発明は、原子力発電所における制御棒位置表示装置に係り、特に、制御棒位置表示系の故障時における制御棒位置の表示技術に関する。
【０００２】
【従来の技術】
従来、この種の制御棒位置表示装置としては、図２に示すように、原子炉制御盤９上の制御棒操作・監視パネル９ａの制御棒選択スイッチ（図示せず）と「挿入」又は「引抜」スイッチ（図示せず）を押すことにより、制御棒駆動補助盤８の制御棒駆動回路８ａに信号を送り、「挿入」又は「引抜」する時間分の制御棒駆動信号(弁動作指示信号)５によって制御棒水圧制御ユニット（ＨＣＵ）４の駆動弁４ｂ１〜４ｂ４を開閉制御し、制御棒２の位置を制御する。この際、制御棒位置を制御棒位置検出プローブ３の制御棒位置信号６を用いて位置表示回路７ａにより原子炉制御盤９上の制御棒操作・監視パネル９ａに表示している。なお、制御棒駆動補助盤８は異常検出回路７ｂを有し、制御棒水圧制御ユニット（ＨＣＵ）４には低圧排出４ａ１、高圧供給４ａ２を備える。
ところで、この制御棒位置表示は、原子炉スクラム動作等の安全保護に係わるものではないため、制御棒位置検出プローブ３による表示のみを行っており、この位置検出プローブ３及び位置表示回路７ａを含む制御棒位置表示系の異常の場合は、バックアップ(代替え)して表示する機能はなかった。
【０００３】
【発明が解決しようとする課題】
上記従来技術は、上述のように、制御棒位置表示系に異常が発生した場合の正しい制御棒位置を表示する機能はない。しかしながら、プラントの安全をより確実に確認するために、制御棒位置の正しい表示は、原子力発電プラントを運転する上で重要な確認項目となっている。
【０００４】
本発明の課題は、重要度の高まった制御棒の位置表示について、制御棒位置表示系に異常が発生した場合に正しい制御棒位置を表示するに好適な制御棒位置表示装置を提供することにある。
【０００５】
【課題を解決するための手段】
上記課題を解決するために、制御棒水圧制御ユニットにより駆動弁を開閉して供給される水の水圧によって制御棒の挿入又は引抜を行い、原子炉の制御棒を操作する制御棒駆動手段と、制御棒の位置を検出する第１の制御棒位置検出手段と、第１の制御棒位置検出手段による検出信号を制御棒位置表示信号として制御棒操作・監視パネルに伝送し、制御棒位置を表示する制御棒位置表示装置において、制御棒を操作する制御棒駆動手段による駆動弁の開閉時間の履歴から制御棒位置を算出する第２の制御棒位置検知手段と、制御棒位置信号切替手段を設け、第１の制御棒位置検出手段に位置検出の故障が発生した時、信号切替手段により、第１の制御棒位置検知手段により検出した制御棒位置表示信号を第２の制御棒位置検知手段によって算出した制御棒位置表示信号に切り替えて制御棒位置を表示する。
ここで、第１の制御棒位置検出手段の動作の正常時には、当該制御棒位置検出手段による制御棒位置表示信号を第２の制御棒位置検知手段に出力し、第２の制御棒位置検知手段により算出した制御棒位置表示信号が第１の制御棒位置検出手段による制御棒位置表示信号と一致するように、前記算出した制御棒位置表示信号を校正する。
【０００６】
【発明の実施の形態】
以下、本発明の実施形態を図面を用いて説明する。
図１図は、本発明による制御棒位置表示装置の一実施形態を示す。
原子力発電所は、核燃料の核分裂反応により熱出力を取り出している。その核燃料の核分裂反応の制御を行うものとして、制御棒にて原子炉内の熱中性子量の制御を行う。制御棒は、中性子吸収材により構成され、原子炉内への挿入量により、中性子の吸収量が変わり、核分裂反応による熱出力制御が可能となる。
この制御棒２は、原子炉１に対して例えば１００本程度が設置されている。制御棒２の手動制御は、原子炉制御盤９上の制御棒操作・監視パネル９ａの制御棒選択スイッチ（図示せず）と「挿入」又は「引抜」スイッチ（図示せず）を押すことにより、制御棒駆動補助盤８の制御棒駆動回路８ａに信号が入り、「挿入」又は「引抜」する時間分の制御棒駆動信号(弁動作指示信号)５を出力する。制御棒駆動回路８ａでは、挿入時と引抜時の挿入引抜指示信号１１（本信号は押ボタンスイッチによるＯＮ、ＯＦＦ信号）が入力され、本信号により、それぞれの駆動弁、すなわち、挿入排出弁（４ｂ１）、引抜供給弁（４ｂ２）、引抜排出弁（４ｂ３）、挿入供給弁（４ｂ４））に対する一定の駆動弁開閉パターンが選択され、駆動弁が開閉する。制御棒駆動信号(弁動作指示信号)５は、それぞれの弁の開閉時間を時系列で定めているＯＮ、ＯＦＦ信号である。
【０００７】
制御棒２は、水圧により「挿入」又は「引抜」がなされる。この水圧は、制御棒水圧制御ユニット（ＨＣＵ）４により供給される。
制御棒水圧制御ユニット（ＨＣＵ）４は、制御棒挿入時は、図３に示すように、挿入供給弁（４ｂ４）を「開」、引抜供給弁（４ｂ２）を「閉」、引抜排出弁（４ｂ３）を「閉」とすることで制御棒挿入側に挿入用の高圧供給４ａ２を行い、かつ、引抜側の圧力を下げるため、挿入排出弁（４ｂ１）を「開」することで制御棒引抜側の圧力を低圧排出４ａ１に逃がし、制御棒の挿入を行う。低圧排出４ａ１および高圧供給４ａ２は、制御棒駆動ポンプ４ａ３に接続され、制御棒駆動ポンプ４ａ３によって加圧された制御棒駆動水を挿入、引抜時に高圧供給４ａ２から入れて低圧排出４ａ１へ抜けるようにしている。
【０００８】
また、制御棒引抜時は、図４に示すように、引抜排出弁（４ｂ３）を「開」することで制御棒挿入側の圧力を低圧排出４ａ１に逃がし、かつ、引抜側の圧力を上げるため、引抜供給弁（４ｂ２）を「開」、挿入供給弁（４ｂ４）を「閉」、挿入排出弁（４ｂ１）を「閉」することで制御棒引抜側に挿入用の高圧供給４ａ２を行うことで制御棒の引抜を行う。
【０００９】
制御棒２の位置は、制御棒引抜ガイド上に設置された複数の制御棒位置検出プローブ３の制御棒位置信号６を制御棒位置指示系盤７の制御棒位置検出回路７ａに入力し、この位置信号６を制御棒位置信号切替回路１０を介して原子炉制御盤９上の制御棒操作・監視パネル９ａに伝送し、表示する。
具体的には、制御棒位置検出プローブ３には位置検出用のリードスイッチが等間隔に例えば４９個設置されており、制御棒駆動ピストンに取付けられた磁石により、その制御棒位置におけるリードスイッチがＯＮ状態となり、制御棒位置が当該位置に設置されたリードスイッチのＯＮ信号により検出され、その情報に基づいて制御棒位置（ノッチ位置）が制御棒位置検出回路７ａに入力され、原子炉制御盤９上の制御棒操作・監視パネル９ａにディジタル数値で表示される。
制御棒位置検出回路７ａの動作状態を異常検出回路７ｂによって監視し、異常時には異常の表示を行う。異常検出回路７ｂでは、例えば駆動指令が出ているのに制御棒の位置信号に変化が無い場合（スティック）を検出し、異常とみなす。また、逆に駆動指令が出ていない時に制御棒の位置信号が変化している場合（ドリフト）を検出し、異常とみなす。
【００１０】
本実施形態においては、制御棒駆動補助盤８の制御棒駆動回路８ａよりの「挿入」又は「引抜」する時間分の制御棒駆動信号(弁動作指示信号)５を制御棒駆動による制御棒位置検知回路８ｂに入力し、制御棒駆動による制御棒位置検知回路８ｂにおいて制御棒位置を算出し、出力を行う。
具体的には、制御棒２は、駆動弁の開閉時間によって制御棒２の挿入引抜き駆動量が一意に決まるため、制御棒駆動信号(弁動作指示信号)５を制御棒水圧制御ユニット４と制御棒駆動による制御棒位置検知回路８ｂの両方に入力し、制御棒位置検知回路８ｂ内で実際に開閉を行った駆動弁の時間履歴を制御棒駆動信号(弁動作指示信号)５を基にデータとして記録し、その履歴を制御棒位置に読み替えることで現在の制御棒位置を検知する。
駆動時間を位置に読み替える方法としては、例えば挿入引抜きにかかる１ノッチ当りの駆動弁動作時間はある値に決まっているため、制御棒駆動信号(弁動作指示信号)５により求まる制御棒の実際の動作時間を１ノッチ当りの駆動弁動作時間で割り算することで制御棒位置に変換する。
例えば、挿入時の制御棒位置を式で表すと、（１）式となる。
制御棒位置＝制御棒現在位置−（制御棒挿入実動作時間／１ノッチ当りの駆動弁動作時間）…（１）
また、引抜き時は（２）式となる。
制御棒位置＝制御棒現在位置＋（制御棒引抜実動作時間／１ノッチ当りの駆動弁動作時間）…（２）
【００１１】
実際に選択して駆動させた制御棒の区別及びその挿入引抜きの区別は、制御棒操作・監視パネル９ａにそれぞれ設けてある「制御棒選択スイッチ」、「挿入」、「引抜」のスイッチを用いて、すなわち「制御棒選択スイッチ」により制御棒を選択し、「挿入」、「引抜」スイッチを押すことによって制御棒を駆動させるため、挿入引抜指示信号１１により制御棒座標、挿入、引抜を区別できる。そこで、挿入引抜指示信号１１の当該情報を制御棒駆動による制御棒位置検知回路８ｂに入力し、１ノッチ当りの駆動弁動作時間で割り算して求めた位置情報と合わせてそれぞれの制御棒位置の検知が可能となる。
【００１２】
この制御棒駆動による制御棒位置検知回路８ｂは、制御棒駆動による制御棒位置信号すなわち制御棒位置（算出）表示信号１３を出力し、制御棒位置検出回路７ａの動作状態が異常検出回路７ｂによって異常時と判定された場合に、制御棒位置検出回路７ａよりの制御棒位置信号６による表示信号と制御棒位置信号切替回路１０にて切り替えを行い、制御棒駆動による制御棒位置（算出）表示信号１３を原子炉制御盤９上の制御棒操作・監視パネル９ａに表示する。
信号切替回路１０は、例えば運転員が制御棒位置信号の異常を判断して手動で切り替える。または、制御棒位置指示系盤７の異常信号（自己診断異常等）により、自動で切り替える。
【００１３】
また、微妙なタイミング（ちょうど、制御棒２にラッチが掛かるか掛からないかの境目）で制御棒２を駆動させた場合、制御棒２の駆動は駆動弁の微妙なタイミングによって１ノッチ変ることがある。従って、制御棒位置検知回路８ｂによる位置算出は、制御棒２の実際の位置から1ノッチ分だけ位置ずれを起こす可能性がある。
従って、制御棒駆動による制御棒位置の正確さを向上させるため、制御棒位置指示系盤７の制御棒位置検出回路７ａの動作が正常な時は常時、制御棒位置（位置検出プローブ）表示信号１２を制御棒駆動による制御棒位置検知回路８ｂに出力し、制御棒駆動による制御棒位置検知回路８ｂにて算出した制御棒位置が制御棒位置（位置検出プローブ）表示信号１２と一致するように、制御棒位置（算出）表示信号１３を校正する。
【００１４】
【発明の効果】
以上説明したように、本発明によれば、制御棒位置表示系に異常が発生した場合、正しい制御棒位置を表示することができ、制御棒位置表示系の異常事態においても原子力発電プラントの安全を確認することができる。
また、制御棒操作の情報に基づいて制御棒位置を算出する制御棒位置（算出）表示信号を制御棒位置表示系の正常時の制御棒位置（位置検出プローブ）表示信号と一致するように、制御棒位置（算出）表示信号を校正することにより、制御棒位置表示系の異常時に、より正しい制御棒位置情報を表示することができる。
【図面の簡単な説明】
【図１】本発明の制御棒位置表示装置の一実施形態の構成図
【図２】従来の制御棒位置表示装置の構成図
【図３】制御棒挿入時の制御棒水圧制御ユニット（ＨＣＵ）の弁動作説明図
【図４】制御棒引抜時の制御棒水圧制御ユニット（ＨＣＵ）の弁動作説明図
【符号の説明】
１…原子炉、２…制御棒、３…制御棒位置検出プローブ、４…制御棒水圧制御ユニット（ＨＣＵ）、４ａ１…低圧排出、４ａ２…高圧供給、４ａ３…制御棒駆動ポンプ、４ｂ１…挿入排出弁、４ｂ２…引抜供給弁、４ｂ３…引抜排出弁、４ｂ４…挿入供給弁、５…制御棒駆動信号、６…制御棒位置信号、７…制御棒位置指示系盤、７ａ…制御棒位置検出回路、７ｂ…異常検出回路、８…制御棒駆動補助盤、８ａ…制御棒駆動回路、８ｂ…制御棒駆動による制御棒位置検知回路、９…原子炉制御盤、９ａ…制御棒操作・監視パネル、１０…制御棒位置信号切替回路、１１…挿入引抜指示信号、１２…制御棒位置（位置検出プローブ）表示信号、１３…制御棒位置（算出）表示信号[0001]
BACKGROUND OF THE INVENTION
The present invention relates to a control rod position display device in a nuclear power plant, and more particularly to a technique for displaying a control rod position when a control rod position display system fails.
[0002]
[Prior art]
Conventionally, as this kind of control rod position display device, as shown in FIG. 2, a control rod selection switch (not shown) on the control rod operation / monitoring panel 9a on the reactor control panel 9 and "insertion" or " By pushing a “pull out” switch (not shown), a signal is sent to the control rod drive circuit 8a of the control rod drive auxiliary board 8 and a control rod drive signal (valve operation instruction signal) corresponding to the “insertion” or “pull out” time. ) 5 controls the opening and closing of the drive valves 4b1 to 4b4 of the control rod water pressure control unit (HCU) 4 to control the position of the control rod 2. At this time, the control rod position is displayed on the control rod operation / monitoring panel 9a on the reactor control panel 9 by the position display circuit 7a using the control rod position signal 6 of the control rod position detection probe 3. The control rod drive auxiliary panel 8 has an abnormality detection circuit 7b, and the control rod water pressure control unit (HCU) 4 is provided with a low pressure discharge 4a1 and a high pressure supply 4a2.
By the way, since the control rod position display is not related to safety protection such as the reactor scram operation, only the display by the control rod position detection probe 3 is performed, and the position detection probe 3 and the position display circuit 7a are included. In the case of an error in the control rod position display system, there was no function to display a backup (substitute).
[0003]
[Problems to be solved by the invention]
As described above, the prior art does not have a function of displaying a correct control rod position when an abnormality occurs in the control rod position display system. However, in order to confirm the safety of the plant more reliably, the correct display of the control rod position is an important confirmation item in operating the nuclear power plant.
[0004]
It is an object of the present invention to provide a control rod position display device suitable for displaying a correct control rod position when an abnormality occurs in the control rod position display system with respect to the position indication of the control rod having increased importance. is there.
[0005]
[Means for Solving the Problems]
In order to solve the above problems, a control rod drive means for operating the control rod of the reactor by inserting or withdrawing the control rod by the water pressure of water supplied by opening and closing the drive valve by the control rod water pressure control unit , a first control rod position detection means for detecting the position of the control rod, and transmitted to the control rod operation and monitoring panel detection signal by the first control rod position detection means as the control rod position 置表示信No., control rod position In the control rod position display device for displaying the control rod, the second control rod position detecting means for calculating the control rod position from the history of the opening and closing time of the drive valve by the control rod driving means for operating the control rod, and the control rod position signal switching means the provided, when the failure of the position detection to the first control rod position detection means is generated by the signal switching means, the first control rod position indication signal detected by the control rod position detection means of the second control rod position detection Calculate by means Switch to the control rod position 置表示信issue to display the control rod position.
Here, the normal time of the operation of the first control rod position detection means outputs a control rod position 置表 No.示信by the control rod position detection means to the second control rod position detection means, the second control rod position control rod position 置表示信No. calculated by the detection means so as to match the control rod position 置表示信No. by the first control rod position detection means for calibrating the control rod position 置表 No.示信that the calculated.
[0006]
DETAILED DESCRIPTION OF THE INVENTION
Hereinafter, embodiments of the present invention will be described with reference to the drawings.
FIG. 1 shows an embodiment of a control rod position display device according to the present invention.
Nuclear power plants extract heat output from nuclear fuel fission reactions. Controlling the nuclear fission reaction of the nuclear fuel, the amount of thermal neutrons in the reactor is controlled by a control rod. The control rod is composed of a neutron absorber, and the amount of neutron absorption varies depending on the amount of insertion into the reactor, and heat output control by fission reaction becomes possible.
For example, about 100 control rods 2 are installed in the nuclear reactor 1. Manual control of the control rod 2 is performed by pressing a control rod selection switch (not shown) and an “insertion” or “extraction” switch (not shown) on the control rod operation / monitoring panel 9a on the reactor control panel 9. Then, a signal enters the control rod drive circuit 8a of the control rod drive auxiliary board 8, and a control rod drive signal (valve operation instruction signal) 5 for the time of “insertion” or “pulling” is output. In the control rod drive circuit 8a, an insertion / extraction instruction signal 11 (this signal is an ON / OFF signal by a pushbutton switch) at the time of insertion and extraction is input, and each drive valve, that is, an insertion / discharge valve ( 4b1), the extraction supply valve (4b2), the extraction discharge valve (4b3), and the insertion supply valve (4b4)) are selected, and the drive valve opens and closes. The control rod drive signal (valve operation instruction signal) 5 is an ON / OFF signal that determines the opening / closing time of each valve in time series.
[0007]
The control rod 2 is “inserted” or “pulled” by water pressure. This water pressure is supplied by a control rod water pressure control unit (HCU) 4.
When the control rod is inserted, the control rod water pressure control unit (HCU) 4 "opens" the insertion supply valve (4b4), "closes" the extraction supply valve (4b2), and draws the extraction discharge valve (4) as shown in FIG. 4b3) is "closed" to supply high pressure 4a2 for insertion to the control rod insertion side, and to pull down the extraction discharge valve (4b1) to reduce the pressure on the extraction side, pull out the control rod The side pressure is released to the low pressure discharge 4a1, and the control rod is inserted. The low-pressure discharge 4a1 and the high-pressure supply 4a2 are connected to the control rod drive pump 4a3, and control rod drive water pressurized by the control rod drive pump 4a3 is inserted and withdrawn from the high-pressure supply 4a2 and pulled out to the low-pressure discharge 4a1. ing.
[0008]
Further, when the control rod is withdrawn, as shown in FIG. 4, in order to release the pressure on the control rod insertion side to the low pressure discharge 4a1 and to raise the pressure on the withdrawal side by opening the withdrawal discharge valve (4b3). By opening the extraction supply valve (4b2), closing the insertion supply valve (4b4), and closing the insertion discharge valve (4b1), the high pressure supply 4a2 for insertion is supplied to the control rod extraction side. Pull out the control rod.
[0009]
The position of the control rod 2 is input to the control rod position detection circuit 7a of the control rod position indicating system board 7 by inputting the control rod position signal 6 of the plurality of control rod position detecting probes 3 installed on the control rod drawing guide. The position signal 6 is transmitted to the control rod operation / monitoring panel 9a on the reactor control panel 9 via the control rod position signal switching circuit 10 and displayed.
Specifically, for example, 49 reed switches for position detection are installed at equal intervals on the control rod position detection probe 3, and the reed switch at the control rod position is set by a magnet attached to the control rod drive piston. The control rod position is detected by the ON signal of the reed switch installed at the position, and the control rod position (notch position) is input to the control rod position detection circuit 7a based on the information, and the reactor control panel 9 on the control rod operation / monitoring panel 9a.
The operation state of the control rod position detection circuit 7a is monitored by the abnormality detection circuit 7b, and an abnormality is displayed when an abnormality occurs. In the abnormality detection circuit 7b, for example, a case where there is no change in the position signal of the control rod (stick) even though a drive command is issued is detected and regarded as abnormal. On the contrary, when the position signal of the control rod is changing (drift) when no drive command is issued, it is detected as abnormal.
[0010]
In this embodiment, the control rod drive signal (valve operation instruction signal) 5 for the time of “insertion” or “pulling” from the control rod drive circuit 8a of the control rod drive auxiliary board 8 is used as the control rod position by the control rod drive. The control rod position is input to the detection circuit 8b, and the control rod position detection circuit 8b by driving the control rod calculates the control rod position and outputs it.
Specifically, since the control rod 2 has a control rod drive signal (valve operation instruction signal) 5 controlled with the control rod hydraulic pressure control unit 4 because the insertion / extraction drive amount of the control rod 2 is uniquely determined by the opening / closing time of the drive valve. Data is input to both of the control rod position detection circuits 8b by rod drive and the time history of the drive valve actually opened and closed in the control rod position detection circuit 8b is based on the control rod drive signal (valve operation instruction signal) 5 And the current control rod position is detected by replacing the history with the control rod position.
As a method for replacing the driving time with the position, for example, the driving valve operating time per notch for insertion / extraction is determined to be a certain value, so the actual control rod obtained from the control rod driving signal (valve operation instruction signal) 5 is used. The operation time is divided by the drive valve operation time per notch to convert to the control rod position.
For example, when the control rod position at the time of insertion is expressed by an expression, the expression (1) is obtained.
Control rod position = Control rod current position− (Control rod insertion actual operation time / drive valve operation time per notch) (1)
In addition, the expression (2) is used at the time of drawing.
Control rod position = Current position of control rod + (actual operation time for pulling out control rod / drive valve operation time per notch) (2)
[0011]
The control rods actually selected and driven and the insertion / extraction are distinguished using the “control rod selection switch”, “insertion”, and “extraction” switches provided on the control rod operation / monitoring panel 9a. In other words, the control rod is selected by the “control rod selection switch”, and the control rod is driven by pressing the “insertion” and “extraction” switches. it can. Therefore, the information on the insertion / extraction instruction signal 11 is input to the control rod position detection circuit 8b by driving the control rod, and the position information obtained by dividing by the drive valve operating time per notch is combined with the position information of each control rod. Detection is possible.
[0012]
The control rod position detection circuit 8b by the control rod drive outputs a control rod position signal by the control rod drive, that is, a control rod position (calculation) display signal 13, and the operation state of the control rod position detection circuit 7a is detected by the abnormality detection circuit 7b. When it is determined that there is an abnormality, the control rod position signal 6 from the control rod position detection circuit 7a is switched by the control rod position signal 6 and the control rod position signal switching circuit 10, and the control rod position (calculation) display by driving the control rod is displayed. The signal 13 is displayed on the control rod operation / monitoring panel 9 a on the reactor control panel 9.
In the signal switching circuit 10, for example, an operator determines that the control rod position signal is abnormal and switches the signal manually. Alternatively, it is automatically switched by an abnormality signal (self-diagnosis abnormality or the like) of the control rod position indicating system panel 7.
[0013]
Further, when the control rod 2 is driven at a delicate timing (just the boundary between whether the control rod 2 is latched or not), the drive of the control rod 2 may change by one notch depending on the delicate timing of the drive valve. is there. Therefore, the position calculation by the control rod position detection circuit 8b may cause a position shift by one notch from the actual position of the control rod 2.
Therefore, in order to improve the accuracy of the control rod position by the control rod drive, the control rod position (position detection probe) display signal is always displayed when the operation of the control rod position detection circuit 7a of the control rod position indicating system board 7 is normal. 12 is output to the control rod position detection circuit 8b by the control rod drive so that the control rod position calculated by the control rod position detection circuit 8b by the control rod drive matches the control rod position (position detection probe) display signal 12. The control rod position (calculation) display signal 13 is calibrated.
[0014]
【The invention's effect】
As described above, according to the present invention, when an abnormality occurs in the control rod position display system, the correct control rod position can be displayed, and even in an abnormal situation of the control rod position display system, Can be confirmed.
Further, the control rod position (calculation) display signal for calculating the control rod position based on the control rod operation information is matched with the normal control rod position (position detection probe) display signal of the control rod position display system. By calibrating the control rod position (calculation) display signal, more accurate control rod position information can be displayed when the control rod position display system is abnormal.
[Brief description of the drawings]
FIG. 1 is a configuration diagram of an embodiment of a control rod position display device of the present invention. FIG. 2 is a configuration diagram of a conventional control rod position display device. FIG. 3 is a control rod hydraulic control unit (HCU) when a control rod is inserted. Explanatory diagram of valve operation of the control rod [Fig. 4] Explanatory diagram of valve operation of the control rod hydraulic pressure control unit (HCU) when the control rod is pulled out
DESCRIPTION OF SYMBOLS 1 ... Nuclear reactor, 2 ... Control rod, 3 ... Control rod position detection probe, 4 ... Control rod hydraulic control unit (HCU), 4a1 ... Low pressure discharge, 4a2 ... High pressure supply, 4a3 ... Control rod drive pump, 4b1 ... Insertion discharge Valve, 4b2 ... drawing supply valve, 4b3 ... drawing discharge valve, 4b4 ... insertion supply valve, 5 ... control rod drive signal, 6 ... control rod position signal, 7 ... control rod position indicating system board, 7a ... control rod position detection circuit 7b ... anomaly detection circuit, 8 ... control rod drive auxiliary panel, 8a ... control rod drive circuit, 8b ... control rod position detection circuit by control rod drive, 9 ... nuclear reactor control panel, 9a ... control rod operation / monitoring panel, DESCRIPTION OF SYMBOLS 10 ... Control rod position signal switching circuit, 11 ... Insertion / extraction instruction signal, 12 ... Control rod position (position detection probe) display signal, 13 ... Control rod position (calculation) display signal

Claims (2)

制御棒水圧制御ユニットにより駆動弁を開閉して供給される水の水圧によって制御棒の挿入又は引抜を行い、原子炉の制御棒を操作する制御棒駆動手段と、前記制御棒の位置を検出する第１の制御棒位置検出手段と、前記第１の制御棒位置検出手段による検出信号を制御棒位置表示信号として制御棒操作・監視パネルに伝送し、前記制御棒位置を表示する制御棒位置表示装置において、
前記制御棒を操作する制御棒駆動手段による前記駆動弁の開閉時間の履歴から制御棒位置を算出する第２の制御棒位置検知手段と、制御棒位置信号切替手段を設け、
前記第１の制御棒位置検出手段に位置検出の故障が発生した時、前記信号切替手段により、前記第１の制御棒位置検知手段により検出した制御棒位置表示信号を前記第２の制御棒位置検知手段によって算出した制御棒位置表示信号に切り替えて制御棒位置を表示することを特徴とする制御棒位置表示装置。 Control rod drive means for operating the control rod of the nuclear reactor, and detecting the position of the control rod by inserting or withdrawing the control rod by the water pressure of water supplied by opening and closing the drive valve by the control rod water pressure control unit a first control rod position detection means transmits a detection signal to the control rod operation and monitoring panel as the control rod position 置表示信No. by the first control rod position detection means, a control rod to display the control rod position In the position display device,
A second control rod position detecting means for calculating a control rod position from a history of opening / closing time of the drive valve by the control rod driving means for operating the control rod, and a control rod position signal switching means;
When a failure of the position detection to the first control rod position detection means is generated, said by the signal switching means, the first said control control rod position indication signal detected by rod position detecting means of the second control rod position control rod position display device and displaying a control rod position is switched to the control rod position 置表示信No. calculated by detecting means. 請求項１において、前記第１の制御棒位置検出手段の動作の正常時には、当該制御棒位置検出手段による制御棒位置表示信号を前記第２の制御棒位置検知手段に出力し、前記第２の制御棒位置検知手段により算出した制御棒位置表示信号が前記第１の制御棒位置検出手段による制御棒位置表示信号と一致するように、前記算出した制御棒位置表示信号を校正することを特徴とする制御棒位置表示装置。According to claim 1, wherein the first to the normal state of the operation of the control rod position detection means outputs a control rod position 置表 No.示信by the control rod position detection means to the second control rod position detection means, said first as control rod position calculated by the second control rod position detection means 置表示信No. coincides with the control rod position 置表示信No. by the first control rod position detection means, the control rod position 置表 shows that the calculated A control rod position display device characterized by calibrating a signal.
JP2003048880A 2003-02-26 2003-02-26 Control rod position display device Expired - Fee Related JP3893563B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2003048880A JP3893563B2 (en) 2003-02-26 2003-02-26 Control rod position display device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2003048880A JP3893563B2 (en) 2003-02-26 2003-02-26 Control rod position display device

Publications (2)

Publication Number Publication Date
JP2004257863A JP2004257863A (en) 2004-09-16
JP3893563B2 true JP3893563B2 (en) 2007-03-14

Family

ID=33114714

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2003048880A Expired - Fee Related JP3893563B2 (en) 2003-02-26 2003-02-26 Control rod position display device

Country Status (1)

Country Link
JP (1) JP3893563B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103400615A (en) * 2013-08-18 2013-11-20 中广核工程有限公司 Rod position indicator

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5020182B2 (en) * 2008-07-25 2012-09-05 日立Ｇｅニュークリア・エナジー株式会社 Reactor control rod controller
JP2015219033A (en) * 2014-05-14 2015-12-07 株式会社日立製作所 Control rod operation monitoring system, control rod individual control part, and testing method for control rod operation monitoring system

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103400615A (en) * 2013-08-18 2013-11-20 中广核工程有限公司 Rod position indicator
CN103400615B (en) * 2013-08-18 2016-05-11 中广核工程有限公司 Rod position indicator

Also Published As

Publication number Publication date
JP2004257863A (en) 2004-09-16

Similar Documents

Publication Publication Date Title
EP2840577B1 (en) Central control device of nuclear power plant
US20040181349A1 (en) Boiler water level monitoring and control system
JP3893563B2 (en) Control rod position display device
EP0088572B1 (en) Systems for monitoring abnormal transient conditions in pressurised water nuclear reactor installations
KR100377103B1 (en) Device for testing performance of hydraulic actuator to regulating turbine steam valve
KR930011109B1 (en) Method of controlling a pwr to prevent overpressure in the event of feed water loss
JP2544856B2 (en) Safety valve operation test device
JP2011164005A (en) Device and method for monitoring control rod driving mechanism
CN108536038B (en) Automatic control simulation system for centrifugal cascade process
JPH05296883A (en) Testing equipment of operation of safety valve
KR101721101B1 (en) Apparatus for generating command signals for control absorber rods of nuclear research reactor and method thereof
JP2002214382A (en) Method and device for testing control rod driving mechanism
JP5020182B2 (en) Reactor control rod controller
JP2002513162A (en) Method and apparatus for monitoring power rise at reactor start-up
CN110838378B (en) Nuclear power plant liquid level switch periodic test control system, control method and storage medium
US4477804A (en) Electrical circuit for providing an abnormal transient display system for nuclear reactor operation
JP4369772B2 (en) Reactor power control method and apparatus
JP4322198B2 (en) Operation control device for nuclear power plant and operation control method for nuclear power plant
JPH0423758B2 (en)
JP2631377B2 (en) Plant control device
JPS6118890A (en) Controller for driving water of control rod for nuclear reactor
KR20210101375A (en) Auxiliary Water Supply Pump Turbine Control System and Method of Nuclear Power Plant
Nguyen et al. Dalat research reactor and its control and instrumentation system renovation
Moray et al. The “Bird's Foot” integrated graphical interface for NPP operation
CN115525042A (en) Fault diagnosis method and device for nuclear power plant equipment

Legal Events

Date Code Title Description
A621 Written request for application examination

Free format text: JAPANESE INTERMEDIATE CODE: A621

Effective date: 20040730

A521 Written amendment

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20041014

A977 Report on retrieval

Free format text: JAPANESE INTERMEDIATE CODE: A971007

Effective date: 20060713

A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20060808

A521 Written amendment

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20061010

TRDD Decision of grant or rejection written
A01 Written decision to grant a patent or to grant a registration (utility model)

Free format text: JAPANESE INTERMEDIATE CODE: A01

Effective date: 20061128

A61 First payment of annual fees (during grant procedure)

Free format text: JAPANESE INTERMEDIATE CODE: A61

Effective date: 20061130

R150 Certificate of patent or registration of utility model

Free format text: JAPANESE INTERMEDIATE CODE: R150

S111 Request for change of ownership or part of ownership

Free format text: JAPANESE INTERMEDIATE CODE: R313111

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20091222

Year of fee payment: 3

R350 Written notification of registration of transfer

Free format text: JAPANESE INTERMEDIATE CODE: R350

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20101222

Year of fee payment: 4

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20101222

Year of fee payment: 4

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20111222

Year of fee payment: 5

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20111222

Year of fee payment: 5

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20121222

Year of fee payment: 6

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20131222

Year of fee payment: 7

LAPS Cancellation because of no payment of annual fees