JPH01112198A - Device for monitoring reactor core during fuel movement - Google Patents
Device for monitoring reactor core during fuel movementInfo
- Publication number
- JPH01112198A JPH01112198A JP62269223A JP26922387A JPH01112198A JP H01112198 A JPH01112198 A JP H01112198A JP 62269223 A JP62269223 A JP 62269223A JP 26922387 A JP26922387 A JP 26922387A JP H01112198 A JPH01112198 A JP H01112198A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- fuel
- control
- reactor core
- monitoring
- 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.)
- Granted
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 90
- 238000012544 monitoring process Methods 0.000 title abstract description 11
- 238000007689 inspection Methods 0.000 claims description 16
- 238000012546 transfer Methods 0.000 claims description 16
- 238000012806 monitoring device Methods 0.000 claims description 14
- 230000000737 periodic effect Effects 0.000 claims description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 238000009835 boiling Methods 0.000 claims description 3
- 230000007246 mechanism Effects 0.000 abstract description 25
- 238000000034 method Methods 0.000 abstract description 8
- 230000008569 process Effects 0.000 abstract description 5
- 235000014676 Phragmites communis Nutrition 0.000 abstract description 2
- 230000009257 reactivity Effects 0.000 description 7
- 238000003780 insertion Methods 0.000 description 6
- 230000037431 insertion Effects 0.000 description 6
- 238000010586 diagram Methods 0.000 description 4
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 238000002955 isolation Methods 0.000 description 3
- 230000002159 abnormal effect Effects 0.000 description 2
- 238000000605 extraction Methods 0.000 description 2
- 230000002265 prevention Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000012790 confirmation Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 238000004904 shortening Methods 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
-
- 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
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力発電プラントの炉心内燃料移動
中に炉心の状態を監視、制御する燃料移動時炉心監視装
置に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a reactor core monitoring device during fuel transfer, which monitors and controls the state of the reactor core during fuel transfer within the core of a boiling water nuclear power plant. .
（従来の技術）
一般に、沸騰水型原子力発電プラントでは、約１カ年毎
に定期検査が実施される。(Prior Art) Generally, in boiling water nuclear power plants, periodic inspections are performed approximately every year.
この定期検査では、各種系統設備の点検が主に行われる
が、原子炉の反応度に影響する点検作業として燃料集合
体の取替えあるいはシャフリングといった燃料（燃料集
合体）の移動、制御棒駆動機構の分解点検、制御棒の取
替え等が行なわれる。This periodic inspection mainly inspects various system equipment, but inspection work that affects the reactivity of the reactor includes replacing fuel assemblies, moving fuel (fuel assemblies) such as shuffling, and controlling rod drive mechanisms. A disassembly and inspection will be carried out, control rods will be replaced, etc.
これらの点検取替え対象本数は運転サイクルによって異
なるが、制御棒駆動機構の分解点検は普通１回につき全
体の１／４が行なわれる。Although the number of these rods to be inspected and replaced varies depending on the operating cycle, one quarter of the total control rod drive mechanism is normally disassembled and inspected at one time.
定期検査工程では、燃料の取替え作業および制御棒駆動
機構の分解点検作業等の炉内構造物に関連する作業は工
程上のクリティカルパスとなっており、定期検査期間短
縮の観点から各作業が一定の範囲内で連続して行なわれ
るよう計画、実施されている。In the periodic inspection process, work related to reactor internal structures, such as fuel replacement work and overhaul inspection of the control rod drive mechanism, is a critical path in the process, and each work is carried out at a certain level in order to shorten the periodic inspection period. It is planned and implemented so that it will be carried out continuously within the scope of.
ところが現状では、原子炉の未臨界性を確保するため炉
心内の制御棒が１本でも引抜かれている場合には、燃料
の移動を禁止するインターロックが設置されているため
、例えば制御棒の引抜を必要とする制御棒駆動機構の点
検は１本ずつ行なう必要があり、■当該制御棒まわりの
燃料の取出しくブレードガイドの移動を含む）→■当該
制御捧の引抜→■制制御馳駆動機構分解・点検→■当該
制御棒の挿入→■制制御まわりへの燃料の装荷といった
手順■■■■■を点検が必要なものの数だけ繰返さなけ
ればならなかった。この作業の期間中は他の燃料の移動
はできないので、全体の作業期間が延び、定期検査期間
が長くなるという問題があった。However, currently, in order to ensure subcriticality of the reactor, interlocks are installed that prohibit the movement of fuel if even one control rod in the reactor core is pulled out. Inspection of the control rod drive mechanism that requires removal must be carried out one by one. ■Including moving the blade guide to remove the fuel around the control rod) → ■Removal of the control rod → ■Control rod drive The procedure of disassembling and inspecting the mechanism → inserting the relevant control rod → loading fuel around the controls had to be repeated as many times as needed to be inspected. Since other fuels cannot be moved during this work, there is a problem in that the overall work period is extended and the regular inspection period becomes longer.
定期検査期間を短縮することは原子カプラントの稼動率
を向上する上で重要であるが、燃料移動作業の面でこれ
を実現するために、■複数の制御棒駆動機構の点検を同
時に実施する、◎制御棒駆動機構の点検と燃料移動を並
行して行なうといった方策が考えられる。ところがこの
ような作業方法は現在のインターロックでは実施できず
、これを行なうには新しいインターロックが必要である
。Shortening the periodic inspection period is important for improving the operating rate of nuclear couplers, but in order to achieve this in terms of fuel transfer work, it is necessary to: ■ carry out inspections of multiple control rod drive mechanisms simultaneously; ◎One possible measure would be to inspect the control rod drive mechanism and move the fuel in parallel. However, this method of operation is not possible with current interlocks and requires a new interlock.
さらにこうした作業は、安全性の観点から原子炉を未臨
界を保ちつつ行なうことが重要である。Furthermore, from a safety perspective, it is important to perform these operations while keeping the reactor subcritical.
（発明が解決しようとする問題点）
本発明はこのような事情を考慮してなされたものであり
、原子炉の燃料移動中に、制御棒の引抜、挿入、燃料の
取出し、装荷作業を監視、制御し、安全にかつ短期間で
燃料移動作業を行なうことのできる燃料移動時炉心監視
装置を得ることを目的としている。(Problems to be Solved by the Invention) The present invention has been made in consideration of the above circumstances, and is designed to monitor control rod withdrawal, insertion, fuel removal, and loading operations during the movement of fuel in a nuclear reactor. The purpose of the present invention is to obtain a core monitoring system during fuel transfer that can control the fuel transfer operation and perform fuel transfer operations safely and in a short period of time.
尚、このような炉心監視装置の有効性は、特願昭５９−
２１５１２７号にも述べられているが、本発明は特に制
御棒の引抜や燃料の装荷を原子炉の未臨界性確保の観点
から制御するところに特徴がある。The effectiveness of such a core monitoring device has been demonstrated in a patent application filed in 1982.
As described in No. 215127, the present invention is particularly characterized in that control rod withdrawal and fuel loading are controlled from the viewpoint of ensuring subcriticality of the reactor.
（問題点を解決するための手段）
本発明は、定期検査時における制御棒の状態に関する各
種信号を入力し、これらの信号に基づいて前記制御棒を
駆動すると異常事態が発生すると判断した時に原子炉手
動制御系に制御棒駆動阻止信号を出力する制御棒監視手
段と、定期検査時における燃料集合体の状態に関する各
種信号を入力し、これらの信号に基づいて燃料交換を行
なうと異常事態が発生すると判断した時に燃料交換機用
計算機に燃料交換機機能停止信号を出力する燃料交換機
監視手段とを備えたことを特徴とする燃料移動時炉心監
視装置である。(Means for Solving the Problems) The present invention inputs various signals related to the state of control rods during regular inspections, and when it is determined that an abnormal situation will occur if the control rods are driven based on these signals, the atomic A control rod monitoring means that outputs control rod drive prevention signals to the reactor manual control system and various signals related to the status of fuel assemblies during periodic inspections are input, and when fuel is replaced based on these signals, an abnormal situation occurs. This apparatus is characterized in that it is equipped with a fuel exchanger monitoring means that outputs a fuel exchanger function stop signal to a fuel exchanger computer when it is determined that the fuel exchanger function is stopped.
（作 用）
本発明の燃料移動時炉心監視装置により、燃料及び制御
棒の操作は常に反応度減少（未臨界方向）になり、安全
な定期検査となる。(Function) With the core monitoring device during fuel transfer of the present invention, the operation of fuel and control rods always reduces the reactivity (in the subcritical direction), resulting in safe periodic inspections.
（実 施 例）
第１図は本発明の一実施例の燃料移動時炉心監視装置を
示すもので、原子炉圧力容器１内に炉心２が収容されて
いる。原子炉圧力容器１の上部には燃料交換機３が配置
されており、炉心２の下方には炉心２内に制御棒４を挿
入する制御棒駆動機構５が配置されている。燃料交換機
３は原子炉建屋最上層に形成されるオペレーティングフ
ロア６に配置され、炉心２と燃料プール間を移動し、主
に燃料謁および第２図に示すブレードガイド２１を掴み
移動する。この燃料交換機３は燃料交換機用計算機７に
より制御される。(Embodiment) FIG. 1 shows a reactor core monitoring device during fuel transfer according to an embodiment of the present invention, in which a reactor core 2 is housed in a reactor pressure vessel 1. As shown in FIG. A fuel exchanger 3 is disposed above the reactor pressure vessel 1, and a control rod drive mechanism 5 for inserting control rods 4 into the reactor core 2 is disposed below the reactor core 2. The fuel exchanger 3 is disposed on an operating floor 6 formed on the top layer of the reactor building, moves between the reactor core 2 and the fuel pool, and mainly moves by grasping the fuel audience and the blade guide 21 shown in FIG. This fuel exchange machine 3 is controlled by a fuel exchange machine computer 7.
すなわち、燃料交換機用計算機７には予めすべての燃料
移動ステップが記憶されており、このプログラムステッ
プに従って燃料交換機３を制御している。なお、各ステ
ップの進行にあたっては制御＃Ｊ４の操作も入るため、
各ステップ毎に運転員による確認が行なわれる。That is, all fuel transfer steps are stored in advance in the fuel exchanger computer 7, and the fuel exchanger 3 is controlled according to these program steps. Furthermore, as each step progresses, control #J4 is also operated.
Confirmation by the operator is performed for each step.
この燃料交換機用計算機７は燃料移動中におけるすべて
の燃料２０およびブレードガイド２１の位置を把握して
おり、そのデータを燃料移動時炉心監視装置８に出力す
る。This fuel exchanger computer 7 grasps the positions of all the fuel 20 and blade guides 21 during fuel movement, and outputs the data to the core monitoring device 8 during fuel movement.
制御棒水圧駆動ユニット９（ＨＣＵ）は制御棒駆動機構
５の駆動ピストン（図示せず）を駆動する。この制御棒
水圧駆動ユニット９は配管、弁、電磁弁および計器等で
構成され、ユニット化されており、制御棒４の本数と同
じ本数設けられている。The control rod hydraulic drive unit 9 (HCU) drives a drive piston (not shown) of the control rod drive mechanism 5. The control rod hydraulic drive unit 9 is composed of pipes, valves, electromagnetic valves, instruments, etc., and is unitized, and is provided in the same number as the control rods 4.
すなわち、制御棒４を駆動する時には制御棒水圧駆動ユ
ニット９の手動隔離弁（図示せず）が開いている状態で
電磁弁（図示せず）が励磁され、水圧が制御棒水圧駆動
ユニット９から制御棒駆動機構５に供給される。この制
御棒水圧駆動ユニット９は対応制御棒４周辺の燃料２ａ
が取り出されている時には、制御棒４の誤挿入による転
倒防止のため隔離弁が閉じられ、制御棒駆動機構５が駆
動することのないよう隔離している。That is, when driving the control rods 4, the solenoid valve (not shown) is energized while the manual isolation valve (not shown) of the control rod hydraulic drive unit 9 is open, and water pressure is transferred from the control rod hydraulic drive unit 9. It is supplied to the control rod drive mechanism 5. This control rod hydraulic drive unit 9 uses fuel 2a around the corresponding control rod 4.
When the control rod 4 is being removed, the isolation valve is closed to prevent the control rod 4 from falling due to incorrect insertion, and the control rod drive mechanism 5 is isolated from being driven.
また、制御棒駆動機構５の分解点検、制御棒水圧駆動ユ
ニッ１−９の点検を行なう際にも隔離される。この制御
棒水圧駆動ユニット９の隔離弁の開閉状態はリミットス
イッチ（図示せず）により検出され、燃料移動時炉心監
視装置８の入力回路に出力される。なお、この制御棒水
圧駆動ユニット９の電磁弁は原子炉手動制御系１０によ
り制御される。It is also isolated when disassembling and inspecting the control rod drive mechanism 5 and inspecting the control rod hydraulic drive unit 1-9. The open/close state of the isolation valve of the control rod hydraulic drive unit 9 is detected by a limit switch (not shown) and output to the input circuit of the core monitoring device 8 during fuel transfer. The solenoid valve of this control rod hydraulic drive unit 9 is controlled by a reactor manual control system 10.
すなわち、制御棒４の操作は原子炉手動制御系１０の手
動スイッチ（図示せず）により行われるが、この原子炉
手動制御系１０の内部には制御棒引抜き阻止回路（図示
せず）が内蔵されており、制御棒４の操作が定期操作か
ら外れている場合に運転員の制御棒４操作を電気的に閉
止する機能を有している。That is, the control rods 4 are operated by a manual switch (not shown) of the reactor manual control system 10, but a control rod withdrawal prevention circuit (not shown) is built into the reactor manual control system 10. It has a function of electrically shutting off the operator's operation of the control rod 4 when the operation of the control rod 4 deviates from the regular operation.
制御棒位置指示系盤１１は制御棒駆動機構５内のリード
スイッチ（図示せず）により検出される制御棒駆動機構
位置信号Ｓ１をデジタル処理し、すべての制御棒駆動機
構位置を監視している。この制御棒位置指示系盤１１は
運転員に制御棒駆動機構５伎置を表示し、またプロセス
計算機（図示せず）にも各種情報を出力しているが、さ
らに燃料移動時炉心監視装置８に制御棒駆動機構５の位
置を示す信号Ｓ２を出力する。The control rod position indication system panel 11 digitally processes a control rod drive mechanism position signal S1 detected by a reed switch (not shown) in the control rod drive mechanism 5, and monitors all control rod drive mechanism positions. . This control rod position indication system panel 11 displays the position of the control rod drive mechanism 5 to the operator and also outputs various information to a process computer (not shown). A signal S2 indicating the position of the control rod drive mechanism 5 is output.
燃料移動時炉心監視装置８は前述したような各種信号を
入力し、制御棒４及び燃料交換機３の動作を制御する。The fuel transfer core monitoring device 8 inputs various signals such as those described above, and controls the operations of the control rods 4 and the fuel exchanger 3.
第２図は炉心２の一部の燃料２０と制御棒４との配置を
示すもので、制御棒４を中心に配置される制御棒とその
周辺の燃料４体をセルという。FIG. 2 shows the arrangement of part of the fuel 20 in the core 2 and the control rods 4. The control rods arranged around the control rod 4 and the four fuel bodies around them are called cells.
図の上部の列は燃料２０が装荷状態であるが、中央列の
左から右へ下部列の左から右までは順に燃料２０を炉外
へ取り出す時のステップを示している。The upper row in the figure shows the fuel 20 in a loaded state, but the middle row from left to right and the lower row from left to right sequentially show steps when the fuel 20 is taken out of the furnace.
制御棒４はそのセル内に燃料２０が対角方向に２体ある
いはブレードガイド２１が存在しない限り、炉心２内で
自立することができない構造となっている。また、ブレ
ードガイド２１は−プラントに少数体しか使用していな
いため、セル内の燃料２０がすベて取り出され制御棒４
が引抜かれた後、他のセルに移動される。The control rod 4 is structured so that it cannot stand on its own within the core 2 unless two fuels 20 or a blade guide 21 are present diagonally within the cell. In addition, since only a small number of blade guides 21 are used in the plant, all of the fuel 20 in the cells is removed from the control rods 4.
is removed and then moved to another cell.
制御棒駆動機構５の点検を行なう際は、制御棒４を全引
抜とする必要があるので、第２図に示すような燃料の移
動、ブレードガイド２１の移動、制御棒４の操作といっ
たステップが繰返されることになる。When inspecting the control rod drive mechanism 5, it is necessary to completely withdraw the control rod 4, so steps such as moving the fuel, moving the blade guide 21, and operating the control rod 4 as shown in FIG. It will be repeated.
第３図は本発明にかかるインターロックの原理を示す説
明図である。炉心２の反応度を変化させる操作として、
制御棒４の引抜、挿入、燃料交換機３による燃料の装荷
、取出しがある。符号（Ａ）。FIG. 3 is an explanatory diagram showing the principle of interlock according to the present invention. As an operation to change the reactivity of the reactor core 2,
There are withdrawal and insertion of the control rod 4, and loading and unloading of fuel by the fuel exchanger 3. Code (A).
（Ｂ）、（Ｃ）は制御棒４とその制御棒セル内の４体の
燃料の状態を示している。すなわち符号（Ａ）は制御棒
全挿入かつ燃料２０が４体とも存在する状態、符号ＣＢ
）は制御棒全引抜（又は制御棒取り出し）かつ燃料２０
が４体とも取り出された状態、符号（Ｃ）は制御棒全引
抜かつ燃料２０が４体とも存在する状態を示している。(B) and (C) show the state of the control rod 4 and the four fuels in its control rod cells. In other words, code (A) is a state in which the control rods are fully inserted and all four fuel bodies are present, and code CB is a state in which all four fuel bodies are present.
) is the control rod fully withdrawn (or control rod removed) and fuel 20
Symbol (C) indicates a state in which all four control rods have been removed and fuel 20 is present in all four control rods.
制御棒４の引抜は、炉心２への反応度投入となるが、こ
の時周りの４体の燃料が取出されていれば（符号（Ｂ）
の状態）、一般に炉心２の反応度は初期の制御棒全挿入
でかつ燃料４体が装荷されている符号（Ａ）の状態より
も低下し、より未臨界の方向となる。一方、燃料を取出
さずに制御棒を引抜いた符号（Ｃ）の状態では、初期状
態（Ａ）よりも臨界に近い方向となり、臨界超過の可能
性もある。Removal of the control rod 4 injects reactivity into the reactor core 2, but if the surrounding four fuel bodies are removed at this time (symbol (B)
In general, the reactivity of the core 2 is lower than in the initial state (A) when the control rods are fully inserted and four fuel bodies are loaded, and becomes more subcritical. On the other hand, in the state (C) in which the control rod is pulled out without removing fuel, the direction is closer to criticality than in the initial state (A), and there is a possibility of overcriticality.
従って各制御棒セルを符号（Ａ）もしくは符号（Ｂ）の
状態となるようにし、符号（Ｃ）の状態を禁止すること
により炉心２の未臨界性を確保することができる。Therefore, the subcriticality of the core 2 can be ensured by placing each control rod cell in the state indicated by symbol (A) or symbol (B) and by prohibiting the state indicated by symbol (C).
このような原理に基づき燃料移動時炉心監視装置８は、
制御棒水圧、駆動ユニット９（ＨＣＵ）からの信号を入
力し、燃料交換機用計算機７からの信号に基づいて第４
図に示すようなフローチャートにより制御棒４の引抜き
操作を監視し、操作が正しい場合には制御棒引抜許可信
号を原子炉手動制御系１０に出力する。操作が誤ってい
る場合にはＣＲＴ２２、あるいは警報器２３に警報信号
を出力する。また、第５図に示すようなフローチャー１
−により制御棒４の挿入操作を監視し、操作が正しい場
合には原子炉手動制御系］０に制御棒挿入許可信号を出
力する。一方、誤っている場合にはＣＲＴ２２あるいは
警報器２３に警報信号を出力する。Based on this principle, the reactor core monitoring device 8 during fuel movement is
The control rod hydraulic pressure and the signal from the drive unit 9 (HCU) are input, and the fourth
The withdrawal operation of the control rod 4 is monitored according to the flowchart shown in the figure, and if the operation is correct, a control rod withdrawal permission signal is output to the reactor manual control system 10. If the operation is incorrect, an alarm signal is output to the CRT 22 or the alarm 23. In addition, flowchart 1 as shown in FIG.
- monitors the insertion operation of the control rod 4, and if the operation is correct, outputs a control rod insertion permission signal to the reactor manual control system]0. On the other hand, if it is incorrect, an alarm signal is output to the CRT 22 or the alarm 23.
さらに、この燃料移動時炉心監視装置８は、燃料交換機
用計算機７からの信号を入力し、第６図に示すようなフ
ローチャートにより燃料集合体の取り出し操作を監視す
る。取り出し操作が正しい場合には燃料交換機用計算機
７に燃料集合体取り出し許可信号を出力し、誤っている
時にはＣＲＴ２２あるいは警報器２３に警報信号を出力
する。Further, this fuel transfer core monitoring device 8 inputs a signal from the refueling machine computer 7, and monitors the fuel assembly removal operation according to a flowchart as shown in FIG. If the extraction operation is correct, a fuel assembly extraction permission signal is output to the fuel exchanger computer 7, and if it is incorrect, an alarm signal is output to the CRT 22 or the alarm 23.
また、第７図に示すようなフローチャートにより燃料集
合体の装荷操作を監視し、正しい時には燃料交換機用計
算機７に装荷許可信号を出力し、誤っている時にはＣＲ
Ｔ２２あるいは警報器２３に警報信号を出力する。In addition, the loading operation of the fuel assembly is monitored according to the flowchart shown in Fig. 7, and when it is correct, a loading permission signal is output to the fuel exchanger computer 7, and when it is incorrect, it is output to the CR.
An alarm signal is output to T22 or alarm device 23.
また、燃料移動時炉心監視装置８は、燃料交換機用計算
機７および制御棒水圧駆動ユニット９からの信号を基に
、燃料交換機３が炉心２上で動作中の際は、原子炉手動
制御系１０に制御棒引抜不許可信号を出力する。逆に、
制御棒４が引抜き中の際は、燃料交換機用計算機７に信
号を送信し、燃料交換機３が炉心２上で動作することを
不許可とする。In addition, the reactor core monitoring device 8 during fuel movement uses the reactor manual control system 10 when the fuel exchanger 3 is operating on the reactor core 2 based on signals from the fuel exchanger computer 7 and the control rod hydraulic drive unit 9. outputs a control rod withdrawal disallowance signal. vice versa,
When the control rods 4 are being withdrawn, a signal is sent to the refueling machine computer 7 to disallow the refueling machine 3 from operating on the core 2.
〔発明の効果〕
以上のような燃料移動時炉心監視装置８の機能により、
第３図の符号（Ａ）、（Ｂ）以外の状態になるのが防止
される。また、反応度投入につながる制御棒４の引抜と
燃料交換機３の炉心２上での動作が同時に行なわれるこ
とが防止される。このため、原子炉に一度に大きな反応
度が加わることがなく、常に未臨界性を確保しつつ安全
に作業を行なうことができる。また、複数の制御棒駆動
機構を同時に点検したり、制御棒駆動機構の点検と燃料
の移動を同時に行なうことができるので、定期検査期間
を短縮しプラントの稼動率を向上することができる。[Effects of the Invention] Due to the functions of the reactor core monitoring device 8 during fuel transfer as described above,
This prevents states other than those shown by symbols (A) and (B) in FIG. 3 from occurring. Further, the withdrawal of the control rods 4 leading to reactivity injection and the operation of the refueling machine 3 on the reactor core 2 are prevented from being performed at the same time. Therefore, a large degree of reactivity is not applied to the nuclear reactor all at once, and work can be carried out safely while always ensuring subcriticality. Furthermore, since it is possible to inspect a plurality of control rod drive mechanisms at the same time, or to inspect the control rod drive mechanisms and move fuel at the same time, it is possible to shorten the periodic inspection period and improve the operating rate of the plant.
第１図は本発明にかかる燃料移動時炉心監視装置を示す
ブロック図、第２図は本発明にががる燃料交換方法を示
す図、第３図は本発明にかがる燃料と制御棒の状態に原
子炉の反応度投入量を示す図、第４図は本発明にかかる
制御棒の引抜き操作を監視するためのフローチャート、
第５図は本発明にかかる制御棒の挿入操作を監視するた
めのフローチャート、第６図は本発明にかかる燃料の取
出し操作を監視するためのフローチャー１・、第７図は
本発明にかかる燃料の装荷操作を監視するためのフロー
チャートである。
３・・・燃料交換機 ４・・・制御棒７・・・燃
料交換機用計算機
８・・・燃料移動時炉心監視装置
ｌＯ・・・原子炉手動制御棒
１１・・・制御棒位置指示系盤
２０・・・燃料 ２１・・・ブレードガイ
ド代理人 弁理士 則 近 憲 佑
同 第子丸 健
第２図
（Ａ） ζＢ）（Ｃ）
虎′料・ 卿目卯ルトの］丈′帖、
第３図
第４図FIG. 1 is a block diagram showing a reactor core monitoring device during fuel transfer according to the present invention, FIG. 2 is a diagram showing a fuel exchange method according to the present invention, and FIG. 3 is a diagram showing fuel and control rods according to the present invention. FIG. 4 is a flowchart for monitoring the control rod withdrawal operation according to the present invention;
FIG. 5 is a flowchart for monitoring the control rod insertion operation according to the present invention, FIG. 6 is a flowchart 1 for monitoring the fuel removal operation according to the present invention, and FIG. 7 is a flowchart according to the present invention. 5 is a flowchart for monitoring fuel loading operations. 3... Fuel exchange machine 4... Control rod 7... Fuel exchange machine computer 8... Core monitoring device during fuel transfer lO... Reactor manual control rod 11... Control rod position indication system panel 20 ...Fuel 21...Blade guide agent Patent attorney Nori Chika Ken Yudo Daishimaru Ken Fig. 2 (A) Figure 4
Claims (1)
に１体でも燃料が装荷されている際は当該制御棒の引抜
を許可せず、制御棒が挿入されていない位置には燃料の
装荷を許可しないインターロックを有することを特徴と
する燃料移動時炉心監視装置。During periodic inspections of boiling water reactors, if even one control rod is loaded with fuel during fuel transfer, the control rod will not be allowed to be withdrawn, and no fuel will be placed in the position where no control rod is inserted. A reactor core monitoring device during fuel movement, characterized by having an interlock that does not permit loading.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62269223A JPH0664173B2 (en) | 1987-10-27 | 1987-10-27 | Fuel transfer core monitoring device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62269223A JPH0664173B2 (en) | 1987-10-27 | 1987-10-27 | Fuel transfer core monitoring device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01112198A true JPH01112198A (en) | 1989-04-28 |
| JPH0664173B2 JPH0664173B2 (en) | 1994-08-22 |
Family
ID=17469377
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62269223A Expired - Lifetime JPH0664173B2 (en) | 1987-10-27 | 1987-10-27 | Fuel transfer core monitoring device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0664173B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH04148896A (en) * | 1990-10-12 | 1992-05-21 | Toshiba Corp | Nuclear reactor surveillance device |
| CN113192661A (en) * | 2021-04-27 | 2021-07-30 | 中国核电工程有限公司 | Rod position monitoring system, rod grid balance judgment method and device, and power control system |
-
1987
- 1987-10-27 JP JP62269223A patent/JPH0664173B2/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH04148896A (en) * | 1990-10-12 | 1992-05-21 | Toshiba Corp | Nuclear reactor surveillance device |
| CN113192661A (en) * | 2021-04-27 | 2021-07-30 | 中国核电工程有限公司 | Rod position monitoring system, rod grid balance judgment method and device, and power control system |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0664173B2 (en) | 1994-08-22 |
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