JPS6357757B2 - - Google Patents
Info
- Publication number
- JPS6357757B2 JPS6357757B2 JP54122824A JP12282479A JPS6357757B2 JP S6357757 B2 JPS6357757 B2 JP S6357757B2 JP 54122824 A JP54122824 A JP 54122824A JP 12282479 A JP12282479 A JP 12282479A JP S6357757 B2 JPS6357757 B2 JP S6357757B2
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- withdrawal
- output
- core
- 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.)
- Expired
Links
- 238000000034 method Methods 0.000 claims description 6
- 238000009835 boiling Methods 0.000 claims description 5
- 238000012544 monitoring process Methods 0.000 claims description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 5
- 230000002265 prevention Effects 0.000 description 7
- 238000010586 diagram Methods 0.000 description 6
- 239000000446 fuel Substances 0.000 description 4
- 238000012806 monitoring device Methods 0.000 description 2
- 230000001771 impaired effect Effects 0.000 description 1
- 229910052724 xenon Inorganic materials 0.000 description 1
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、沸騰水型原子炉の制御棒引抜監視方
法に係り、特に高出力運転時の制御棒誤引抜に伴
う過度の出力上昇を防止する技術に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a control rod withdrawal monitoring method for a boiling water nuclear reactor, and particularly to a technique for preventing an excessive increase in power due to control rod erroneous withdrawal during high power operation.
一般に、沸騰水型原子炉においては、高出力運
転時に制御棒を連続引抜することは、局所的な出
力の急上昇をもたらす。 Generally, in a boiling water reactor, continuous withdrawal of control rods during high-power operation results in a local sudden increase in power.
そのため、誤操作等により、この事態の発生す
ることを防止する方策が必要とされる。 Therefore, measures are required to prevent this situation from occurring due to erroneous operation or the like.
従来、制御棒は、その全ストロークを複数段に
分け、一段ずつ段階的に引抜くことができるノツ
チ引抜と、さらに起動時に、制御棒引抜時間を短
縮するため連続的に引抜くことができる連続引抜
とがある。 Conventionally, control rods have been withdrawn in a notched manner, in which the entire stroke is divided into multiple stages, and can be withdrawn step by step, and in a continuous manner, in which the control rod can be withdrawn continuously at startup to shorten the control rod withdrawal time. There is a withdrawal.
しかし、現在の原子炉では、両者を特別に区別
して取扱つてはいない。 However, in current nuclear reactors, there is no special distinction between the two.
ところで、沸騰水型原子炉では、炉心の出力調
整手段として、制御棒とともに炉心流量制御を有
する。 By the way, a boiling water reactor has a core flow rate control as well as a control rod as a means for adjusting the core output.
そのため第１図に示すように、制御棒引抜は、
炉心流量の小さい、炉心出力の低い領域で行な
い、流量上昇により、定格出力を達成する方法が
とられている。 Therefore, as shown in Figure 1, control rod withdrawal is
The method used is to perform this in a region where the core flow rate is low and the core output is low, and by increasing the flow rate, the rated output is achieved.
第１図は、ある運転例の炉心出力対炉心流量の
特性曲線で、点１から点２までは制御棒引抜が行
なわれ、点２から点３までは流量増加による出力
上昇を表わしている。 FIG. 1 is a characteristic curve of core power versus core flow rate for a certain operation example, from point 1 to point 2 control rod withdrawal is performed, and from point 2 to point 3 represents an increase in output due to an increase in flow rate.
そのため、高出力領域では、制御棒引抜は行な
わないか、又は行なわれても大規模な引抜とはな
らない。 Therefore, in the high power range, control rod withdrawal is not performed, or even if control rod withdrawal is performed, it is not large-scale withdrawal.
たとえば、制御棒の全ストロークを、24ノツチ
に分ける場合では、１ノツチ程度の引抜となる。 For example, if the entire stroke of the control rod is divided into 24 notches, the withdrawal will be about one notch.
そのため、高出力時では制御棒の連続引抜を必
ずしも必要としていない。 Therefore, continuous withdrawal of control rods is not necessarily required at high output.
一方、予備的解析によれば、第２図に示すよう
に、出力運転中に制御棒を１本、全挿入状態から
連続引抜することとし、初期状態を100％とする
と、局所的に約135％程度まで出力が上昇するこ
とがわかつている。ここで引抜率100％とは全引
抜を表わす。 On the other hand, according to preliminary analysis, as shown in Figure 2, one control rod is continuously withdrawn from the fully inserted state during power operation, and assuming the initial state is 100%, locally about 135 It is known that the output increases up to about %. Here, 100% withdrawal rate means complete withdrawal.
そのため、仮に、定格出力附近で運転員の誤操
作等により、このような制御棒引抜が起つたとす
ると、燃料の健全性上大きな影響があると考えら
れる。 Therefore, if such a control rod were to be pulled out due to operator error near the rated output, it would have a major impact on the health of the fuel.
ここにおいて、本発明は、上記の点に鑑み、炉
心出力が一定レベル以上では、制御棒連続引抜を
阻止することにより、高出力運転時の制御棒誤引
抜に伴う過度の出力上昇を防止することを目的と
する。 In view of the above points, the present invention prevents continuous withdrawal of control rods when the core output exceeds a certain level, thereby preventing an excessive increase in power due to erroneous withdrawal of control rods during high-power operation. With the goal.
本発明は、平均出力モニターから出力された炉
心出力信号をもとに、炉心出力を設定値と比較
し、もし、炉心出力が設定値より大きければ、制
御棒連続引抜阻止信号を出し、もし炉心出力が設
定値より小さければ、制御棒連続引抜を許す信号
を出力するようにしたものである。 The present invention compares the core power with a set value based on the core power signal output from the average power monitor, and if the core power is greater than the set value, a control rod continuous withdrawal prevention signal is issued, and if the core If the output is smaller than the set value, a signal is output that allows continuous withdrawal of the control rods.
第３図は、本発明の一実施例にかかるブロツク
図である。２０１は炉心、２０２は制御棒、２０
３は制御棒制御装置、２０５は平均出力モニタ、
２０６は制御棒連続引抜監視装置、２１１は炉心
出力信号、２１２は制御棒連続引抜阻止信号、２
１３は制御棒操作信号、２１４はLPRM（ローカ
ル・パワー・レンジ・モニタ、Local Power
Range Monitor）信号である。 FIG. 3 is a block diagram according to an embodiment of the present invention. 201 is the reactor core, 202 is the control rod, 20
3 is a control rod control device, 205 is an average output monitor,
206 is a control rod continuous withdrawal monitoring device, 211 is a core output signal, 212 is a control rod continuous withdrawal prevention signal, 2
13 is the control rod operation signal, 214 is the LPRM (Local Power Range Monitor)
Range Monitor) signal.
平均出力モニタ２０５はLPRM信号２１４を
用いて、常に炉心の出力をモニタしており、安定
した作動をし、その信号は信頼でき、かつ容易に
使用することができる。 The average power monitor 205 constantly monitors the power of the core using the LPRM signal 214, operates stably, and its signal is reliable and easy to use.
設定値としては、現在の知見によれば、約70％
の定格出力から約85％定格出力の間に設定するの
が適当と考えられる。 According to current knowledge, the setting value is approximately 70%.
It is considered appropriate to set the value between the rated output of 1 and approximately 85% of the rated output.
その根拠は、以下の通り。 The basis for this is as follows.
第４図は引抜阻止設定値例の説明図である。点
２′から点３に至る曲線は流量制御曲線、４は炉
心出力67％の直線、５はその出力約70％の直線、
６は連続引抜阻止設定値例を表わす出力直線、７
はその出力約85％の直線、８はその出力100％の
直線、９は炉心流量が最低流量の直線、１０はそ
の流量100％の直線を表わす。 FIG. 4 is an explanatory diagram of an example of pull-out prevention setting values. The curve from point 2' to point 3 is the flow control curve, 4 is the straight line at 67% of the core power, 5 is the straight line at about 70% of the core power,
6 is an output straight line representing an example of continuous withdrawal prevention setting value, 7
8 represents the straight line at approximately 85% of the power output, 8 represents the straight line at 100% of the power, 9 represents the straight line at the lowest core flow rate, and 10 represents the straight line at 100% of the flow rate.
第４図に示すように、現在の原子炉では100％
定格出力100％定格流量（点３）からXe（キセノ
ン）平衡を保つたまま流量を最低（約40％）まで
下げるとその出力は約76％となる（直線４）。そ
のため、それ以上に設定しておけば、最抵流量時
の制御棒連続引抜を妨げることはない。そのた
め、設定値の下限を約70％とした。 As shown in Figure 4, in current nuclear reactors, 100%
If the flow rate is lowered from 100% rated output (point 3) to the minimum (approximately 40%) while maintaining Xe (xenon) balance, the output will be approximately 76% (straight line 4). Therefore, if it is set higher than this, continuous withdrawal of the control rod at the maximum resistance flow will not be hindered. Therefore, the lower limit of the set value was set at approximately 70%.
次に、燃料設計上では、燃料の出力が設計上の
定格値116％においても、健全性が保たれること
を仮定している。 Next, in fuel design, it is assumed that soundness is maintained even when the fuel output is 116% of the design rated value.
一方、上記予備解析によれば、制御棒連続引抜
時の出力上昇は、初期値の135％程度である。 On the other hand, according to the above preliminary analysis, the increase in output during continuous control rod withdrawal is about 135% of the initial value.
そこで、もし初期出力が86％以下であれば、連
続的に制御棒を全挿入より全引抜しても、そのと
きの燃料の出力上昇は、設計上の定格値の
86％×1.35＝116％
で限度内に納まる。 Therefore, if the initial output is 86% or less, even if the control rods are continuously withdrawn from the fully inserted position, the increase in fuel output will be 86% of the design rated value x 1.35 = 116%. is within the limits.
これから、約85％定格出力を設定値の上昇とし
た。そして、本例はやや余裕をみて低目に設定し
てある。なお、上記の設定値の設定範囲は、炉心
特性等の変更に伴い改められ得るものである。 From now on, the set value will be increased to approximately 85% of the rated output. In this example, the value is set low to give some margin. Note that the setting range of the above-mentioned setting values may be changed in accordance with changes in core characteristics and the like.
しかして、制御棒２０２が引抜されようとする
場合、たとえば制御棒選択信号を制御棒制御装置
２０４より受けると、平均出力モニタ２０５から
出された炉心出力信号２１１を用いて、炉心出力
が予め設定された値より大きいか否かを判定す
る。 When the control rod 202 is about to be withdrawn, for example, when a control rod selection signal is received from the control rod controller 204, the core power is set in advance using the core power signal 211 output from the average power monitor 205. Determine whether the value is greater than the specified value.
出力が設定値を超えている場合、制御棒連続引
抜阻止信号２１２を出す。 If the output exceeds the set value, a control rod continuous withdrawal prevention signal 212 is issued.
その場合、制御棒に１ノツチ引抜のみ可能とな
る。 In that case, only one notch in the control rod can be withdrawn.
出力が設定値以下の場合は、制御棒連続引抜許
可信号を出す。 If the output is below the set value, a control rod continuous withdrawal permission signal is issued.
この場合は、制御棒は１ノツチ引抜および連続
引抜の両方が可能となる。 In this case, the control rod can be withdrawn both in one notch and continuously.
かくして、本発明により、高出力運転時の制御
棒連続引抜が阻止されるため、制御棒誤引抜によ
る過度の出力上昇を防止することができる。 Thus, according to the present invention, continuous withdrawal of control rods during high-output operation is prevented, so that an excessive increase in output due to erroneous withdrawal of control rods can be prevented.
そして、高出力時に、制御棒を連続引抜するこ
とができなくなるが、通常、高出力時に制御棒を
大幅に引抜くことはない。仮に制御棒引抜が必要
な場合でも、１ノツチごとの引抜はできるため、
運転は支障をきたすことはない。 At high outputs, the control rods cannot be continuously withdrawn, but normally the control rods are not withdrawn to a large extent at high outputs. Even if it is necessary to withdraw the control rod, it can be done one notch at a time, so
Driving is not impaired.
第１図は沸騰水型原子炉の運転例における炉心
出力対炉心流量特性曲線、第２図は出力運転時の
制御棒連続引抜における出力と引抜率の予備的解
析説明図、第３図は本発明一実施例にかかるブロ
ツク図、第４図はこの実施例における引抜阻止設
定例の説明図である。
２０１……炉心、２０２……制御棒、２０３…
…制御棒駆動機構、２０４……制御棒制御装置、
２０５……平均出力モニタ、２０６……制御棒連
続引抜監視装置、２１１……炉心出力信号、２１
２……制御棒連続引抜阻止信号、２１３……制御
棒操作信号、２１４……LPRM信号。
Figure 1 is a characteristic curve of core power versus core flow rate in an operation example of a boiling water reactor, Figure 2 is a preliminary analysis explanatory diagram of power and withdrawal rate in continuous control rod withdrawal during power operation, and Figure 3 is a diagram of this book. FIG. 4, a block diagram according to an embodiment of the invention, is an explanatory diagram of an example of a pull-out prevention setting in this embodiment. 201...Reactor core, 202...Control rod, 203...
...Control rod drive mechanism, 204...Control rod control device,
205... Average power monitor, 206... Control rod continuous withdrawal monitoring device, 211... Core output signal, 21
2... Control rod continuous withdrawal prevention signal, 213... Control rod operation signal, 214... LPRM signal.
Claims (1)
に引抜く機構を具備する沸騰水型原子炉の制御棒
駆動機構を制御・監視する制御棒引抜監視方法に
おいて、炉心出力対炉心流量の特性曲線上の最低
流量時における制御棒連続引抜を妨げることのな
い値に設定値を設け、この設定値以上に炉心出力
が上昇した場合、制御棒を複数段一度に引抜くこ
とを阻止し一段ごとの引抜のみを許すようにした
ことを特徴とする制御棒引抜監視方法。 ２ 設定値を約70％定格出力から約85％定格出力
までの間の値に設定することを特徴とする特許請
求の範囲第１項に記載の制御棒引抜監視方法。[Scope of Claims] 1. In a control rod withdrawal monitoring method for controlling and monitoring a control rod drive mechanism of a boiling water reactor, which is equipped with a mechanism for dividing the entire stroke of a control rod into multiple stages and withdrawing it in stages, A set value is set at a value that does not prevent continuous withdrawal of control rods at the lowest flow rate on the characteristic curve of core flow rate, and when the core power increases beyond this set value, control rods are withdrawn in multiple stages at once. A method for monitoring control rod withdrawal, characterized in that the control rod withdrawal is prevented and only withdrawal of each stage is allowed. 2. The control rod withdrawal monitoring method according to claim 1, wherein the set value is set to a value between about 70% rated output and about 85% rated output.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP12282479A JPS5646493A (en) | 1979-09-25 | 1979-09-25 | Control rod blocking monitor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP12282479A JPS5646493A (en) | 1979-09-25 | 1979-09-25 | Control rod blocking monitor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5646493A JPS5646493A (en) | 1981-04-27 |
| JPS6357757B2 true JPS6357757B2 (en) | 1988-11-14 |
Family
ID=14845534
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP12282479A Granted JPS5646493A (en) | 1979-09-25 | 1979-09-25 | Control rod blocking monitor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5646493A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0697269B2 (en) * | 1985-11-15 | 1994-11-30 | 株式会社東芝 | How to operate a nuclear reactor |
-
1979
- 1979-09-25 JP JP12282479A patent/JPS5646493A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5646493A (en) | 1981-04-27 |
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