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JPH0687079B2 - Reactor operation control method - Google Patents
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JPH0687079B2 - Reactor operation control method - Google Patents

Reactor operation control method

Info

Publication number
JPH0687079B2
JPH0687079B2 JP63129846A JP12984688A JPH0687079B2 JP H0687079 B2 JPH0687079 B2 JP H0687079B2 JP 63129846 A JP63129846 A JP 63129846A JP 12984688 A JP12984688 A JP 12984688A JP H0687079 B2 JPH0687079 B2 JP H0687079B2
Authority
JP
Japan
Prior art keywords
control rod
output
absorption control
deviation
reactor
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
JP63129846A
Other languages
Japanese (ja)
Other versions
JPH01299495A (en
Inventor
明男 田村
博之 壇
義信 高橋
孝 金川
良治 ▲吉▼木
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.)
Hokkaido Electric Power Co Inc
Kansai Electric Power Co Inc
Kyushu Electric Power Co Inc
Japan Atomic Power Co Ltd
Shikoku Electric Power Co Inc
Mitsubishi Heavy Industries Ltd
Original Assignee
Hokkaido Electric Power Co Inc
Kansai Electric Power Co Inc
Kyushu Electric Power Co Inc
Japan Atomic Power Co Ltd
Shikoku Electric Power Co Inc
Mitsubishi Heavy Industries 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 Hokkaido Electric Power Co Inc, Kansai Electric Power Co Inc, Kyushu Electric Power Co Inc, Japan Atomic Power Co Ltd, Shikoku Electric Power Co Inc, Mitsubishi Heavy Industries Ltd filed Critical Hokkaido Electric Power Co Inc
Priority to JP63129846A priority Critical patent/JPH0687079B2/en
Publication of JPH01299495A publication Critical patent/JPH01299495A/en
Publication of JPH0687079B2 publication Critical patent/JPH0687079B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 [産業上の利用分野] 本発明は、例えば加圧水型原子炉において、出力変化を
伴う運転に対し適用される原子炉の運転制御方法に関す
る。
Description: TECHNICAL FIELD The present invention relates to a reactor operation control method applied to an operation involving a change in output, for example, in a pressurized water reactor.

[従来の技術] 例えば加圧水型原子炉において、負荷の変化に対応した
原子炉の出力変化を伴う運転は、次の3種類の基本モー
ドに分けられ、それらを単独、あるいはそれらを重ね合
わせて運転される。
[Prior Art] For example, in a pressurized water reactor, an operation involving a change in the output of the reactor corresponding to a change in load is divided into the following three basic modes, which are operated alone or in combination with each other. To be done.

(1)予め、決められた出力変化パターンに基づく運転
モード (2)外部からの要求に応じてランダムに出力を変化さ
せる運転モード (3)周波数調整等のため、外部からの要求、あるいは
負荷の変化に応じ自動的に出力を変化させる運転モード である。
(1) Operation mode based on a predetermined output change pattern (2) Operation mode in which output is changed randomly in response to external demand (3) External demand or load This is an operation mode that automatically changes the output according to changes.

一般に、原子炉の出力変化幅に対する要求は、前記
(1),(2),(3)の順で高く、出力変化に対する
要求頻度は前記(3),(2),(1)の順で高い。
Generally, the demand for the power variation range of a nuclear reactor is high in the order of (1), (2), (3), and the demand frequency for the power variation is in the order of (3), (2), (1). high.

従来は、これらの運転に対し、複数の群を持つ一種類の
制御棒グループの移動と、一時冷却材中のほう素濃度の
手動調整により、反応度調整を行っていたが、この方法
では出力変化率が大きい場合、出力分布、歪を制限値内
にするという観点から出力変化幅の小さいものに限定さ
れてしまい、前記(1)の運転モードに対して制限が加
えられる。
Conventionally, for these operations, reactivity was adjusted by moving one type of control rod group with multiple groups and manually adjusting the boron concentration in the temporary coolant. When the rate of change is large, the range of output change is limited from the viewpoint of keeping the output distribution and distortion within the limit values, and the operation mode of (1) above is limited.

そこで、この点を解消するため、出力分布に対する影響
程度の異なる2種類の制御棒グループを用いる方法が提
案されている。
Therefore, in order to eliminate this point, a method of using two types of control rod groups having different degrees of influence on the output distribution has been proposed.

この具体的な例として、特公昭58-34795号公報に示すよ
うに、出力分布に対する影響の小さい方の制御棒グルー
プ(以下、弱吸収制御棒と称す)の挿入度をタービン要
求出力の関数として一意的に決定するとともに、出力分
布に対する影響の大きい方の制御棒グループ(以下、強
吸収制御棒と称す)は、一次冷却材平均温度の基準値か
らの偏差に応じて移動し、かつ軸方向出力分布偏差に応
じて行なわれるほう素の調整による平均温度の変化を通
して軸方向出力分布偏差を所定の範囲に収める方法(以
下、F法と称す)である。
As a concrete example of this, as shown in Japanese Patent Publication No. 58-34795, the insertion degree of a control rod group (hereinafter referred to as a weak absorption control rod), which has a smaller effect on the power distribution, is a function of the turbine required output. The control rod group that is uniquely determined and has a greater effect on the power distribution (hereinafter referred to as the strong absorption control rod) moves according to the deviation from the reference value of the primary coolant average temperature, and the axial direction. This is a method of keeping the axial power distribution deviation within a predetermined range by changing the average temperature by adjusting boron, which is performed according to the power distribution deviation (hereinafter referred to as the F method).

またこのF法とは別に、特願昭61-206836号明細書に示
すように、強吸収制御棒を出力変化時や、それに伴って
生じる一次冷却材平均温度の基準値からの偏差に応じて
移動し、強吸収制御棒は軸方向出力分布偏差に応じて移
動させ、それによる平均温度偏差を通じて強吸収制御棒
の移動により、軸方向出力分布偏差偏差を所定の範囲に
収め、ほう素濃度の調整は、もっぱら弱吸収制御棒の補
助として用いる方法(以下、M法)である。
In addition to the F method, as shown in Japanese Patent Application No. 61-206836, the output of the strong absorption control rod changes and the deviation of the average primary coolant temperature from the reference value occurs in accordance with the output change. Then, the strong absorption control rod is moved according to the axial power distribution deviation, and the strong absorption control rod is moved through the average temperature deviation thereby, so that the axial power distribution deviation deviation is kept within a predetermined range. The adjustment is a method (hereinafter, referred to as M method) used exclusively as an auxiliary for the weak absorption control rod.

以上述べたF法とM法では、それぞれ性能に次のような
差がある。一般に、前記(1)〜(3)のごとき運転に
対する性能は、主に次の点で評価される。
The above-mentioned F method and M method have the following differences in performance. In general, the performances for the above operations (1) to (3) are evaluated mainly in the following points.

(4)負荷パターンに対する任意性すなわち、急激な負
荷変化や予定外のランダムな負荷変化に対する追従性 (5)水処理量 ほう素濃度調整に伴う排出水を処理する必要があるが、
プラントの処理水量は、ほう素濃度の調整幅が大きいと
多くなる。また、調整幅が同程度であっても、一次冷却
材中のほう素濃度の低下に伴って水処理量は増加する。
従って、ほう素濃度調整への依存度の高い運転方法の場
合、炉心寿命末期において、負荷追従運転が制限され
る。
(4) Arbitraryness to load pattern, that is, followability to sudden load changes and unplanned random load changes (5) Water treatment amount It is necessary to treat the discharged water accompanying the boron concentration adjustment,
The amount of treated water in the plant increases as the boron concentration adjustment range increases. Further, even if the adjustment range is about the same, the water treatment amount increases as the boron concentration in the primary coolant decreases.
Therefore, in the case of the operating method having a high dependency on the boron concentration adjustment, the load following operation is limited at the end of the life of the core.

(6)機器への負担 出力変化を伴う種々のパラメータ変動により、各制御機
器の動作回数が増加するが、特に制御棒駆動機構は、取
替えが困難なため、制御棒移動量が過多とならないこと
が必要である。
(6) Burden on equipment The number of operations of each control equipment increases due to various parameter fluctuations that accompany changes in output, but especially because the control rod drive mechanism is difficult to replace, the control rod movement amount should not be excessive. is necessary.

(7)設備コスト 負荷追従運転を行うための必要な設備コストである。(7) Equipment cost This is the equipment cost required to perform load following operation.

[発明が解決しようとする課題] ところが、前記(1)〜(3)のように出力変化を含む
原子炉の運転においては、一般に制御棒、ほう素等の制
御要素は、燃料の燃焼に伴う、長期的な炉心反応度の調
整の他に次の2つの反応変化を補償する必要がある。
[Problems to be Solved by the Invention] However, in the operation of a nuclear reactor including output changes as described in (1) to (3) above, control elements such as control rods and boron are generally accompanied by combustion of fuel. In addition to long-term core reactivity adjustment, it is necessary to compensate for the following two reaction changes.

(8)出力変化に伴う減速材と燃料の温度変化によって
生じる反応度変化(以下、出力欠損と称す)。
(8) Change in reactivity caused by change in temperature of moderator and fuel due to change in output (hereinafter referred to as output loss).

(9)出力変化によって生じる炉心内のキセノン(以
下、Xeと称す)の量の変化による反応度変化(以下、Xe
欠損と称す)。
(9) Changes in reactivity due to changes in the amount of xenon (hereinafter referred to as Xe) in the core caused by changes in power (hereinafter referred to as Xe
Called a defect).

前記Fの方法では、弱吸収制御棒は実質的には、前記出
力欠損のを補償するように挿入されるため、いかなる時
点でも急速に全出力復帰ができ、前記(2)の如き、ラ
ンダムな出力変化要求に対しての適応性がある反面前記
Xe欠損の補償は、実質的にはほう素濃度の調整のみによ
っているため、前記(5)で述べた水処理量が多くなり
好ましくない。また、前記(3)の運転を行う場合、非
常に頻繁な出力変化があるが、この方法のように弱吸収
制御棒位置が、出力の一意的な関数として制御される場
合、前記(3)の運転に伴う出力欠損は、弱吸収制御棒
のみで補償されることとなり、その反応度価値の小ささ
により、制御棒移動量が過多となり、前記(6)のよう
な問題がある。
In the method of F, since the weak absorption control rod is substantially inserted so as to compensate for the loss of the output, the full output can be rapidly returned at any time, and the random absorption like the above (2) is performed. Although it is adaptable to output change requirements, the above
Compensation for the Xe deficiency is substantially only by adjusting the boron concentration, so the amount of water treatment described in (5) above becomes large, which is not preferable. Further, when performing the operation of (3) above, there is a very frequent output change, but when the weak absorption control rod position is controlled as a unique function of output as in this method, the above (3) The output deficiency due to the operation of is compensated only by the weak absorption control rod, and the control rod movement amount becomes excessive due to the small reactivity value, and there is a problem as described in (6) above.

前記Mの方法では、以上述べたFの方法の問題点ば解決
できるが、軸方向出力分布偏差を、弱吸収制御棒の移動
による一次冷却材平均温度の変化を通じて強吸収制御棒
により修正する関係上、両グループの制御棒の相互干渉
を避けるため、弱吸収制御棒の出力分布に与える影響を
前記Fの方法に比べて大幅に小さくする必要があり、必
然的に必要な制御棒の体数が増加し、前記(7)の問題
点が生じる。
The method of M can solve the problems of the method of F described above, but the relationship in which the axial power distribution deviation is corrected by the strong absorption control rod through the change of the primary coolant average temperature due to the movement of the weak absorption control rod Moreover, in order to avoid mutual interference between the control rods of both groups, it is necessary to make the influence on the output distribution of the weak absorption control rods much smaller than that of the above method F, and the number of control rods required is inevitable. Increases, causing the problem (7) above.

そこで、本発明は比較的少数体の制御棒で要求される負
荷追従能力を確保でき、水処理量を削減できる原子炉の
運転制御方法を提供することを目的とする。
Therefore, it is an object of the present invention to provide a reactor operation control method capable of ensuring the load following ability required by a relatively small number of control rods and reducing the amount of water treatment.

[課題を解決するための手段] 本発明は、前記目的を達成するため、原子炉容器の炉心
に挿脱される制御棒として弱吸収制御棒と強吸収制御棒
とを備え、原子炉冷却材の平均温度偏差算出装置と軸方
向出力分布偏差算出装置を有する原子炉を運転するに際
し、原子炉冷却材の平均温度偏差と軸方向出力分布偏差
(ΔI)とを監視し、前記強吸収制御棒を引抜き又は挿
入によって、前記原子炉冷却材の平均温度偏差と前記軸
方向出力分布偏差とが共に小さくなる場合に前記強吸収
制御棒を駆動し、前記の場合以外では前記弱吸収制御棒
を駆動して前記炉心内の反応度を調整することを特徴と
する原子炉の運転制御方法である。
[Means for Solving the Problems] In order to achieve the above object, the present invention includes a weak absorption control rod and a strong absorption control rod as control rods that are inserted into and removed from the core of a reactor vessel, and In operating a nuclear reactor having the average temperature deviation calculating device and the axial power distribution deviation calculating device, the average temperature deviation of the reactor coolant and the axial power distribution deviation (ΔI) are monitored to detect the strong absorption control rod. By pulling or inserting, the strong absorption control rod is driven when both the average temperature deviation of the reactor coolant and the axial power distribution deviation are small, and the weak absorption control rod is driven in other cases. Then, the reactivity of the reactor is adjusted to control the operation of the reactor.

[作用] 前記のように強吸収制御棒と弱吸収制御棒を平均温度の
偏差に応じていずれかを選択して移動させることによ
り、比較的少数体の制御棒で要求される負荷追従能力を
確保でき、かつ水処理量を削減できる。
[Operation] As described above, by selecting either the strong absorption control rod or the weak absorption control rod according to the deviation of the average temperature and moving the rod, the load following ability required by a relatively small number of control rods can be obtained. It can be secured and the amount of water treatment can be reduced.

[実施例] 以下、本発明の実施例について図面を参照して説明する
が、初めに第1図により本発明の運転制御方法の概念に
ついて説明する。一次冷却材平均温度の基準値からの偏
差信号によって弱吸収制御棒GR、あるいは強吸収制御棒
Dが次式で示す軸方向出力分布偏差ΔIに応じて選択さ
れ、かつ駆動される。この選択は、その時点における軸
方向出力分布偏差ΔIの制御目標値からの偏差が、その
制御棒移動が強吸収制御棒Dで行なわれた場合に、温度
偏差と同時に修正される場合には、強吸収制御棒Dが選
択され、それ以外の場合や目標値からの偏差が、強吸収
制御棒を移動した場合により大きくなる場合には、軸方
向出力分布偏差ΔIへの影響の少ない弱吸収制御棒GRが
選択されるように行う。
[Embodiment] An embodiment of the present invention will be described below with reference to the drawings. First, the concept of the operation control method of the present invention will be described with reference to FIG. The weak absorption control rod GR or the strong absorption control rod D is selected and driven according to the axial output distribution deviation ΔI represented by the following equation by the deviation signal from the reference value of the primary coolant average temperature. This selection is made when the deviation of the axial output distribution deviation ΔI from the control target value at that time is corrected simultaneously with the temperature deviation when the control rod movement is performed by the strong absorption control rod D. If the strong absorption control rod D is selected, and in other cases or if the deviation from the target value becomes larger due to the movement of the strong absorption control rod, the weak absorption control with less influence on the axial output distribution deviation ΔI. Do so that bar GR is selected.

ΔI=PT−PB PT:炉心上半分の出力の炉心定格出力に対する比(%) PB:炉心下半分の出力の炉心定格出力に対する比(%) 次に、第2図により、前記軸方向出力分布偏差ΔIによ
る駆動制御棒選択の概念について説明する。一次冷却材
平均温度の基準値との偏差つまり温度偏差ΔTが負の場
合すなわち引き続き要求の場合は、強吸収制御棒Dを引
抜くと、軸方向出力分布偏差ΔIは正側に移行するた
め、第2図(a)に示すごとく、ΔIが制御目標に対し
ある程度(例えば2%)以上負側となっている場合[第
2図(a)の斜線部]には強吸収制御棒Dが選択され、
それ以外の場合には弱吸収制御棒GRが選択される。同様
に、温度偏差ΔTが正で、制御棒を挿入する場合には全
く逆であり、第2図(b)のごとくΔIが制御目標に対
し、ある程度(例えば2%)以上正側の偏差を持ってい
る場合[第2図(b)の斜線部]には、強吸収制御棒D
が選択され、かつ挿入され、それ以外の場合には、弱吸
収制御棒GRが選択され、かつ挿入される。
ΔI = P T −P B P T : Ratio of upper half power to rated core power (%) P B : Ratio of lower half power to core rated power (%) Next, referring to FIG. The concept of drive control rod selection based on the axial output distribution deviation ΔI will be described. When the deviation from the reference value of the primary coolant average temperature, that is, the temperature deviation ΔT is negative, that is, when the demand is continued, when the strong absorption control rod D is pulled out, the axial output distribution deviation ΔI shifts to the positive side. As shown in FIG. 2A, when ΔI is on the negative side to some extent (for example, 2%) with respect to the control target [shaded portion in FIG. 2 (a)], the strong absorption control rod D is selected. Is
In other cases, the weak absorption control rod GR is selected. Similarly, when the temperature deviation ΔT is positive and the control rod is inserted, the opposite is true, and as shown in FIG. 2 (b), ΔI is a deviation on the positive side to some extent (for example, 2%) or more from the control target. If you have [the shaded area in Fig. 2 (b)], the strong absorption control rod D
Is selected and inserted, otherwise the weak absorption control rod GR is selected and inserted.

このような方法により、制御棒の移動は、その時点での
出力分布から見て最良の方が駆動されることになり、制
御棒の無駄な動きを無視し、かつ2種類の制御棒の相互
干渉を無視して制御できる。また、第2図のごとき選択
指標の場合で、前記(3)の運転に際し、弱吸収制御棒
GRが選択駆動される場合が多く、結果として、弱吸収制
御棒GRの移動量が多くなり、前記(6)の問題が生じる
場合には、第2図中の制御目標に対する制御棒選択の境
界線(図の実線)の位置を変え、例えば設定値を変更す
ることにより対処できる。すなわち、第2図(a)に対
しては、境界線をΔI正側(図の右側)に、第2図
(b)に対してはΔI負側(図の左側)へずらしていく
に従い、弱吸収制御棒移動量は減少し、強吸収制御棒移
動量は増加する。
With such a method, the control rod is moved in the best way from the viewpoint of the output distribution at that time, ignoring the useless movement of the control rod, and controlling the mutual movement of the two types of control rods. Control can be performed by ignoring interference. Moreover, in the case of the selection index as shown in FIG. 2, the weak absorption control rod is used during the operation of (3) above.
In many cases, the GR is driven selectively, and as a result, the amount of movement of the weak absorption control rod GR increases, and when the problem of (6) above occurs, the control rod selection boundary with respect to the control target in FIG. This can be dealt with by changing the position of the line (solid line in the figure) and changing the set value, for example. That is, as shown in FIG. 2 (a), the boundary line is shifted to the ΔI positive side (right side of the figure), and to FIG. 2 (b) to the ΔI negative side (left side of the figure). The amount of weak absorption control rod movement decreases and the amount of strong absorption control rod movement increases.

なお、この場合、その制御棒価値の差により強吸収制御
棒移動量の増加分は、弱吸収制御棒移動量の減少分より
も少なくなる。第3図は第2図において、弱吸収制御棒
移動量を少なくするために、境界線をずらした場合で、
第3図(a)は温度偏差が負すなわち引き抜き要求の場
合であり、第3図(b)は温度偏差が正すなわち挿入要
求の場合である。
In this case, the increase amount of the strong absorption control rod movement amount becomes smaller than the decrease amount of the weak absorption control rod movement amount due to the difference in the control rod value. FIG. 3 shows a case where the boundary line is shifted in order to reduce the movement amount of the weak absorption control rod in FIG.
FIG. 3 (a) shows the case where the temperature deviation is negative, that is, the drawing request, and FIG. 3 (b) shows the case where the temperature deviation is positive, that is, the insertion request.

次に、本発明の実施例について説明するが、ここで制御
の対象としているのは、4ループの加圧水型原子炉に対
するものであり、弱吸収制御棒としてはその中性子吸収
能力が上下軸方向で下半分が小さく、上半分が大きく設
定されたものを4本を1群とし、2群構成で用いてい
る。
Next, an example of the present invention will be described. Here, the object of control is for a 4-loop pressurized water reactor, and the weak absorption control rod has a neutron absorption capability in the vertical axis direction. The lower half is set small and the upper half is set large, and four are used as one group and used in a two-group configuration.

第4図は弱吸収制御棒移動範囲の例を示すもので、横軸
は相対出力を示し、縦軸は弱吸収制御棒挿入度を示して
いる。図の実線の引き抜き制限と破線の挿入限界とで囲
まれる範囲内であれば、弱吸収制御棒は、一次冷却材平
均温度偏差に応じて、軸方向出力分布偏差の値により、
弱吸収制御棒が選択される場合に駆動され、出力欠損の
みならずXe欠損の一部又は全部を補償することにより、
水処理量の削減が図かれる。即ち、弱吸収制御棒の典型
的な動きは次の通りである。
FIG. 4 shows an example of the weak absorption control rod moving range, in which the horizontal axis represents relative output and the vertical axis represents the weak absorption control rod insertion degree. Within the range surrounded by the drawing limit of the solid line and the insertion limit of the broken line in the figure, the weak absorption control rod, according to the primary coolant average temperature deviation, by the value of the axial power distribution deviation,
Driven when the weak absorption control rod is selected, by compensating not only the output loss but also a part or all of the Xe loss,
The amount of water treatment can be reduced. That is, the typical movement of the weak absorption control rod is as follows.

(a)出力低下時、平均温度の正側偏差の増大により順
次挿入→(b)出力低下完了後、Xeの蓄積に伴う負側の
温度偏差により引抜き→(c)引抜き制限まで引き抜か
れた場合は停止→(d)部分出力状態が長い場合、Xeの
崩壊に伴う正側の温度偏差により挿入→(e)出力上昇
時、負側の温度偏差により引抜き。
(A) When the output is decreased, the average temperature is sequentially inserted due to an increase in the deviation on the positive side → (b) After the output has been decreased, it is pulled out due to the temperature deviation on the negative side due to the accumulation of Xe → (c) When the extraction limit is pulled out Is stopped → (d) If the partial output state is long, insert due to the positive side temperature deviation due to the collapse of Xe → (e) When the output rises, pull out due to the negative side temperature deviation.

一般に、第4図に示す挿入限界は、停止余裕の確保等の
炉心の安全性上の観点から必要に応じて設定すればよ
く、引き抜き制限は運用上そのプラントに要求される部
分出力状態からの急速出力復帰能力によって決定され
る。すなわち、第4図の引き抜き制限ラインを図の下方
に設定すれば、急速出力復帰能力が向上し、上方に設定
すれば、ほう素濃度に対する要求量すなわち水処理量が
減少する。
Generally, the insertion limit shown in FIG. 4 may be set as necessary from the viewpoint of the safety of the core such as securing a stop margin, and the pulling-out limit is set from the partial output state required for the plant in operation. Determined by rapid output recovery capability. That is, if the pulling-out restriction line in FIG. 4 is set to the lower part of the drawing, the rapid output recovery capability is improved, and if it is set to the upper part, the required amount for the boron concentration, that is, the water treatment amount is reduced.

第5図は第4図に示した弱吸収制御棒移動範囲を用いた
前記(1)の運転に対する模擬計算結果を示すものであ
る。図中G1,G2はそれぞれ弱吸収制御棒の第1群,第2
群であり、50%出力で第2群G2を全引抜きまで許されて
おり、またDは強吸収制御棒である。この図から明らか
なように、全出力から1時間で50%出力まで出力低下
し、50%出力を8時間保持した後1時間で全出力に復帰
している。そして、弱吸収制御棒は前記のように移動
し、かつΔIの変動もわずかな範囲に制御されている。
FIG. 5 shows a simulation calculation result for the operation (1) using the weak absorption control rod moving range shown in FIG. In the figure, G1 and G2 are the first and second groups of weak absorption control rods, respectively.
The second group G2 is allowed up to full withdrawal at 50% output, and D is a strong absorption control rod. As is clear from this figure, the output decreased from the full output to 50% output in 1 hour, and after the 50% output was maintained for 8 hours, the full output was restored in 1 hour. Then, the weak absorption control rod moves as described above, and the fluctuation of ΔI is controlled within a slight range.

第6図は、ほう素濃度変化に対する効果を明らかにする
ため、弱吸収制御棒挿入度を出力の関数とした場合に対
する計算結果を示している。第5図に示した本発明によ
る運転制御方法によりほう素濃度変化幅、すなわち水処
理量が大幅に削減されていることがわかる。
FIG. 6 shows calculation results for the case where the weak absorption control rod insertion degree is used as a function of the output in order to clarify the effect on the boron concentration change. It can be seen that the range of change in boron concentration, that is, the amount of water treated is greatly reduced by the operation control method according to the present invention shown in FIG.

第7図は本発明による制御系の基本構成を示すもので、
制御棒駆動要求信号、選択のための信号ΔIによる
制御棒駆動系とともに、ΔI偏差によるほう素濃度変化
要求、制御棒位置がその限界に達した際のほう素濃度
変化要求によるほう素濃度制御系により制御する。
FIG. 7 shows the basic configuration of the control system according to the present invention.
A control rod drive request signal, a control rod drive system by a signal ΔI for selection, a boron concentration change request by a ΔI deviation, and a boron concentration control system by a boron concentration change request when the control rod position reaches its limit. Controlled by.

以上述べた本発明による実施例によれば、弱吸収制御棒
GRが一定出力の下でも自由に移動し得る範囲を設定し、
この範囲内で一次冷却材平均温度の基準値からの温度偏
差ΔTに応じて移動させることにより、弱吸収制御棒GR
によって出力欠損のみならず、Xe欠損の少なくとも一部
を補償できる。また、強吸収制御棒Dと弱吸収制御棒GR
を平均温度の偏差に応じてどちらかを選択して移動させ
る方法をとり、かつその選択の指標として軸方向出力分
布の制御を良好なものとし、かつ片方の制御棒移動量の
みが増大しないように軸方向出力分布偏差信号を用いて
いることから、比較的少数体の制御棒で要求される負荷
追従能力を確保でき、水処理量を削減できる。
According to the embodiment of the present invention described above, the weak absorption control rod
Set the range where the GR can move freely even under constant output,
By moving the primary coolant average temperature in this range according to the temperature deviation ΔT from the reference value, the weak absorption control rod GR
Can compensate not only the output loss but also at least part of the Xe loss. In addition, strong absorption control rod D and weak absorption control rod GR
Is selected according to the deviation of the average temperature and moved, and the control of the axial power distribution is made good as an index for the selection, and only one control rod movement amount does not increase. Since the axial power distribution deviation signal is used for the, it is possible to secure the load following ability required by a relatively small number of control rods and reduce the amount of water treatment.

[発明の効果] 以上述べた本発明によれば、比較的少数体の制御棒で要
求される負荷追従能力を確保でき、水処理量を削減でき
る原子炉の運転制御方法を提供できる。
[Effects of the Invention] According to the present invention described above, it is possible to provide a reactor operation control method capable of ensuring the load following ability required by a relatively small number of control rods and reducing the amount of water treatment.

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

第1図は本発明の原子炉の運転制御方法の概念を説明す
るための図、第2図は第1図において軸方向出力分布偏
差ΔIによる制御棒選択の概念を説明するための図、第
3図は第2図における弱吸収制御棒移動量を少なくする
方法を説明するための図、第4図は本発明による弱吸収
制御棒移動範囲の設定例を示す図、第5図は本発明によ
る運転制御方法を用いた場合の負荷値追従運転時のパラ
メータ変化を示す図、第6図は従来の運転方法による負
荷追従運転時のパラメータ変化を示す図、第7図は本発
明における制御系の基本構成を示す図である。 GR……弱吸収制御棒、D……強吸収制御棒、ΔI……軸
方向出力分布偏差、ΔI……一次冷却材平均温度偏差。
1 is a diagram for explaining the concept of a nuclear reactor operation control method of the present invention, FIG. 2 is a diagram for explaining the concept of control rod selection based on the axial power distribution deviation ΔI in FIG. 1, FIG. 3 is a diagram for explaining a method for reducing the amount of weak absorption control rod movement in FIG. 2, FIG. 4 is a diagram showing an example of setting the weak absorption control rod movement range according to the present invention, and FIG. 5 is the present invention. FIG. 6 is a diagram showing parameter changes during load value following operation when the operation control method according to FIG. 6 is used, FIG. 6 is a diagram showing parameter changes during load following operation according to the conventional operation method, and FIG. 7 is a control system according to the present invention. It is a figure which shows the basic composition of. GR: Weak absorption control rod, D: Strong absorption control rod, ΔI: Axial output distribution deviation, ΔI: Primary coolant average temperature deviation.

───────────────────────────────────────────────────── フロントページの続き (71)出願人 999999999 日本原子力発電株式会社 東京都千代田区大手町1丁目6番1号 (71)出願人 999999999 三菱重工業株式会社 東京都千代田区丸の内2丁目5番1号 (72)発明者 田村 明男 大阪府大阪市北区中之島3丁目3番22号 関西電力株式会社内 (72)発明者 壇 博之 福岡県福岡市中央区渡辺通2丁目1番82号 九州電力株式会社内 (72)発明者 高橋 義信 東京都千代田区大手町1丁目6番1号 日 本原子力発電株式会社内 (72)発明者 金川 孝 東京都港区芝公園2丁目4番1号 三菱原 子力工業株式会社内 (72)発明者 ▲吉▼木 良治 東京都港区芝公園2丁目4番1号 三菱原 子力工業株式会社内 ─────────────────────────────────────────────────── ─── Continuation of the front page (71) Applicant 999999999 Japan Atomic Power Company 1-6-1, Otemachi, Chiyoda-ku, Tokyo (71) Applicant 999999999 2-5-1 Marunouchi, Chiyoda-ku, Tokyo Mitsubishi Heavy Industries, Ltd. No. (72) Inventor Akio Tamura 3-3-22 Nakanoshima, Kita-ku, Osaka City, Osaka Prefecture Kansai Electric Power Co., Inc. (72) Hiroyuki Dan, 2-1-2 Watanabe-dori, Chuo-ku, Fukuoka-shi, Fukuoka Kyushu Electric Power Co., Inc. In-house (72) Inventor Yoshinobu Takahashi 1-6-1, Otemachi, Chiyoda-ku, Tokyo Nihon Nuclear Power Co., Inc. (72) In-house Takashi Kanagawa 2-4-1, Shiba-koen, Minato-ku, Tokyo Mitsubishi Hara Within Riki Kogyo Co., Ltd. (72) Inventor ▲ Yoshi ▼ Ryoji Ki, 2-4-1, Shiba Park, Minato-ku, Tokyo Inside Mitsubishi Harako Riki Kogyo Co., Ltd.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】原子炉容器の炉心に挿脱される制御棒とし
て弱吸収制御棒と強吸収制御棒とを備え、原子炉冷却材
の平均温度偏差算出装置と軸方向出力分布偏差算出装置
を有する原子炉を運転するに際し、原子炉冷却材の平均
温度偏差と軸方向出力分布偏差(ΔI)とを監視し、前
記強吸収制御棒を引抜き又は挿入によって、前記原子炉
冷却材の平均温度偏差と前記軸方向出力分布偏差とが共
に小さくなる場合に前記強吸収制御棒を駆動し、前記の
場合以外では前記弱吸収制御棒を駆動して前記炉心内の
反応度を調整することを特徴とする原子炉の運転制御方
法。
1. A weak absorption control rod and a strong absorption control rod are provided as control rods that are inserted into and removed from a core of a reactor vessel, and a reactor coolant average temperature deviation calculation device and an axial power distribution deviation calculation device are provided. When operating the reactor, the average temperature deviation of the reactor coolant and the axial power distribution deviation (ΔI) are monitored, and the average temperature deviation of the reactor coolant is extracted by pulling out or inserting the strong absorption control rod. And the axial power distribution deviation are both small, the strong absorption control rod is driven, and in other cases, the weak absorption control rod is driven to adjust the reactivity in the core. Reactor operation control method.
JP63129846A 1988-05-27 1988-05-27 Reactor operation control method Expired - Fee Related JPH0687079B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63129846A JPH0687079B2 (en) 1988-05-27 1988-05-27 Reactor operation control method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63129846A JPH0687079B2 (en) 1988-05-27 1988-05-27 Reactor operation control method

Publications (2)

Publication Number Publication Date
JPH01299495A JPH01299495A (en) 1989-12-04
JPH0687079B2 true JPH0687079B2 (en) 1994-11-02

Family

ID=15019685

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63129846A Expired - Fee Related JPH0687079B2 (en) 1988-05-27 1988-05-27 Reactor operation control method

Country Status (1)

Country Link
JP (1) JPH0687079B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP3038076U (en) * 1996-11-21 1997-06-06 育子 工藤 Car side mirror
KR20160084048A (en) * 2015-01-05 2016-07-13 한국수력원자력 주식회사 Monitoring method for axial zone flux tilt of heavy water reactor and apparatus using the monitoring method

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8699653B2 (en) * 2011-10-24 2014-04-15 Westinghouse Electric Company, Llc Method of achieving automatic axial power distribution control
CN116246802A (en) * 2022-12-12 2023-06-09 中广核研究院有限公司 Reactor control method, device, computer equipment and storage medium

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP3038076U (en) * 1996-11-21 1997-06-06 育子 工藤 Car side mirror
KR20160084048A (en) * 2015-01-05 2016-07-13 한국수력원자력 주식회사 Monitoring method for axial zone flux tilt of heavy water reactor and apparatus using the monitoring method

Also Published As

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JPH01299495A (en) 1989-12-04

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