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JPH027436B2 - - Google Patents
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JPH027436B2 - - Google Patents

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Publication number
JPH027436B2
JPH027436B2 JP56004606A JP460681A JPH027436B2 JP H027436 B2 JPH027436 B2 JP H027436B2 JP 56004606 A JP56004606 A JP 56004606A JP 460681 A JP460681 A JP 460681A JP H027436 B2 JPH027436 B2 JP H027436B2
Authority
JP
Japan
Prior art keywords
output
change
control rod
bank
changes
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 - Lifetime
Application number
JP56004606A
Other languages
Japanese (ja)
Other versions
JPS57119297A (en
Inventor
Hiroshi Tochihara
Shunichi Uchinami
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
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 Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP56004606A priority Critical patent/JPS57119297A/en
Publication of JPS57119297A publication Critical patent/JPS57119297A/en
Publication of JPH027436B2 publication Critical patent/JPH027436B2/ja
Granted 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
    • 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】 この発明は加圧水型原子炉の負荷追従運転方法
に関するものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a load following operation method for a pressurized water nuclear reactor.

近来、原子力発電において負荷追従能力が望ま
れている。すなわち、従来、全発電量における原
子力発電量の割合が小さかつたために、原子力発
電に対しては負荷追従能力が期待されなかつた
が、近来、原子力発電量の全発電量に対する割合
が大きくなるに及んで、原子力発電においても負
荷追従能力が望まれるに到り、これに伴つて、炉
心出力を追従させる必要が生ずるに到り、さらに
炉心の反応度制御を追従させて行う必要が生じる
に到つた。負荷追従運転のように炉心の出力変動
がある場合の反応度変化は主として第1図に典型
例で示しているように、出力レベル変化に伴なう
反応度変化(これを出力欠損という)およびキノ
セン(Xe)変化による反応度変化の2つから成
り立つている。出力欠損は、第2図に典型例を示
しているように、燃料温度変化によるドツプラー
効果の出力欠損分と1次冷却材の炉心平均温度変
化による出力欠損分の合計となる。ドツプラー出
力欠損の方は、炉心の寿命中あまり変化しないが
温度変化の出力欠損の方は寿命末期になるにした
がつて大きくなる。全体の出力欠損は第3図に典
型例を示すように寿命末期で大きくなつてくる。
Recently, load following ability has been desired in nuclear power generation. In other words, in the past, the proportion of nuclear power generation in total power generation was small, so nuclear power generation was not expected to have the ability to follow the load, but in recent years, as the proportion of nuclear power generation in total power generation has increased. As a result, load following capability has come to be desired in nuclear power generation as well, and along with this, it has become necessary to follow the reactor core output, and it has also become necessary to follow the reactor core reactivity control. Ivy. Changes in reactivity when the core output fluctuates, such as during load-following operation, are mainly caused by changes in reactivity due to changes in output level (this is called power loss), as shown in a typical example in Figure 1. It consists of two factors: a change in reactivity due to a change in quinocene (Xe). As a typical example is shown in FIG. 2, the power loss is the sum of the power loss due to the Doppler effect due to the fuel temperature change and the power loss due to the core average temperature change of the primary coolant. The Doppler power loss does not change much during the life of the core, but the power loss due to temperature changes increases towards the end of the core life. The overall output loss becomes large at the end of the life, as shown in a typical example in FIG.

加圧水型原子炉の反応度制御装置としては、従
来から、制御棒およびほう素濃度変化系があり、
制御棒は、速い反応度変化を可能にし、ほう素濃
度変化系は1次冷却材中のほう素濃度を増減させ
て遅い反応度変化を可能にするから、出力変動中
の反応度変化のうち、出力欠損分は制御棒挿入、
引抜で補償すれば早い出力変化にも対応でき、
Xe変化分はゆつくりした変化であるのでほう素
濃度変化で対応すればよいと一応は考えられる。
Reactivity control devices for pressurized water reactors have traditionally included control rods and boron concentration change systems.
The control rods enable fast reactivity changes, and the boron concentration change system increases or decreases the boron concentration in the primary coolant to enable slow reactivity changes, so most of the reactivity changes during output fluctuations are , insert a control rod to compensate for the output loss,
If you compensate by pulling out, you can respond to quick output changes.
Since the Xe change is a slow change, it is thought that it can be dealt with by changing the boron concentration.

しかし、100%から50%出力への変化では出力
欠損は約0.7%Δρ程度あり、一方制御に通常使わ
れる制御棒バンクDは全挿入で約1.0〜1.4%Δρ程
度の制御棒ワースがあるので、制御棒だけで出力
欠損分を補償しようとすると制御棒を炉心の中央
より下へ深く挿入する必要がある。制御棒を深く
挿入すると軸方向出力分布が大きく歪んで来てそ
の後Xeによる出力分布振動等も起つて来て問題
となる。このような軸方向出力分布歪みを避ける
ために最近では制御棒をあまり深く挿入しないで
出力変動をすることが標準的運転法となつてい
る。この場合、制御棒だけでは出力欠損を補償で
きないので、残りの反応度はほう素濃度変化によ
ることになり、速い出力変動ができないことにな
る。また、低下した出力レベルから元の全出力レ
ベルに即時に復帰する即時復帰能力も、当然制御
棒が出力欠損分だけ深く挿入されていないので不
足してくることになる。第4図に従来の標準的な
負荷追従運転中の出力レベル変化、制御棒挿入度
およびほう素濃度変化を図示するが、この第4図
から明らかなように制御棒は炉心にあまり深く挿
入されないので速い出力変動能力および即時復帰
能力に不足があり、それらの問題の解決が望まれ
ている。また、炉心出力の制御方法として、いく
つかの技術(例えば特公51−47837号公報、特開
54−17498号公報参照)が提案されているが満足
すべき結果を得るに至つていない。
However, when changing from 100% to 50% output, the output loss is about 0.7% Δρ, while control rod bank D, which is normally used for control, has a control rod worth of about 1.0 to 1.4% Δρ when fully inserted. In order to compensate for the power loss with only the control rods, it is necessary to insert the control rods deep below the center of the reactor core. If the control rod is inserted deeply, the axial power distribution will be greatly distorted, and power distribution vibration due to Xe will also occur, which becomes a problem. In order to avoid such axial power distribution distortion, it has recently become a standard operating method to vary the power without inserting the control rods too deeply. In this case, since the control rod alone cannot compensate for the power loss, the remaining reactivity will depend on changes in boron concentration, and rapid power fluctuations will not be possible. Furthermore, the instantaneous return ability to immediately return to the original full output level from a reduced output level will naturally be insufficient because the control rods are not inserted as deep as the output loss. Figure 4 shows changes in output level, degree of control rod insertion, and boron concentration changes during conventional standard load following operation.As is clear from Figure 4, the control rods are not inserted very deeply into the core. Therefore, there is a lack of quick output fluctuation ability and immediate recovery ability, and a solution to these problems is desired. In addition, some techniques (for example, Japanese Patent Publication No. 51-47837, Japanese Unexamined Patent Publication No. 51-47837,
54-17498) has been proposed, but no satisfactory results have been obtained.

この発明は上記の如き事情に鑑みてなされたも
のであつて、炉心の軸方向出力分布に大きな歪を
生じさせることなく、炉心の速い出力変化及び即
時復帰能力を容易に実現し得る加圧水型原子炉の
運転方法を提供することを目的とするものであ
る。
This invention has been made in view of the above circumstances, and is a pressurized water type atom that can easily realize rapid power change and immediate return capability of the reactor core without causing large distortions in the axial power distribution of the reactor core. The purpose is to provide a method for operating a furnace.

この目的に対応して、この発明の加圧水型原子
炉の負荷追従運転方法は、加圧水型原子炉の負荷
追従運転における出力変化による反応度変化分に
ほぼ等価な制御棒価値を有する制御棒バンクをバ
ンクオーバーラツプが無いか若しくはバンクオー
バーラツプが小さい状態で炉心に挿入し、出力低
下を急速に行いその後のキセノン増加による反応
度減少はほう素濃度変化により補償し、その後の
出力上昇にあたつては制御棒引抜により出力変化
による反応度変化分を補償し、出力上昇後のキセ
ノン減少による反応度増加はほう素濃度変化によ
り補償する運転方法において、制御棒挿入による
アキシヤルオフセツト変化のカーブが負側の最大
値を越えて更に制御棒を挿入するとアキシヤルオ
フセツトの絶対値が減少する範囲である炉心下部
近傍を制御棒の操作範囲とすることを特徴として
いる。
In response to this purpose, the load following operation method for a pressurized water reactor of the present invention provides a control rod bank having a control rod value approximately equivalent to a change in reactivity due to a change in output during load following operation of a pressurized water reactor. The reactor is inserted into the core with no bank overlap or with a small bank overlap, and the power is rapidly reduced.The subsequent decrease in reactivity due to the increase in xenon is compensated for by changes in boron concentration, and the subsequent increase in power is compensated for by changes in boron concentration. In the future, in an operating method in which the change in reactivity due to the change in output is compensated for by withdrawing the control rod, and the increase in reactivity due to the decrease in xenon after the increase in output is compensated for by the change in boron concentration, the change in axial offset due to the insertion of the control rod is It is characterized in that the control rod operation range is set near the bottom of the core, which is the range where the absolute value of the axial offset decreases when the control rod is further inserted after the curve exceeds the maximum value on the negative side.

以下この発明の詳細を一実施例について説明す
る。
The details of this invention will be explained below with reference to one embodiment.

まず、重要な点として、この発明では炉心に制
御棒を挿入する場合にバンクオーバーラツプを設
けずに、バンクオーバーラツプがないか或いはバ
ンクオーバーラツプがきわめて僅かであるように
して挿入する。すなわち、炉心の軸方向出力分布
歪みの指標であるアキシヤルオフセツト(A.O.)
は、qT,qBをそれぞれ炉心上半分及び下半分の
出力とすると、 A.O.=qT−qB/qT+qB×100(%) で定義される。従来の制御棒バンクは各バンク間
の反応度の連続性を良くするために第5図Aに示
すように、バンクオーバーラツプと称して各バン
クがある程度かさなりあつて挿入されるようにな
つている。すなわち、通常の例では最初のバンク
が128ステツプ(全体のステツプは228ステツプ)
になると次のバンクが同時に挿入され始めるわけ
である。このため、制御棒を挿入して行くとアキ
シヤルオフセツトは第6図の線Aで示す如くどん
どん負側に大きくなり元にはもどらない。したが
つて、従来の方法では制御棒をある程度深く挿入
すると必然的にA.O.は負側で大になり、出力分
布制御が難しくなつたわけである。しかるに、こ
の発明のように、第5図Bに示す如く、制御棒バ
ンクのオーバーラツプをなくして各バンクを独立
に挿入すると、制御棒を全挿入に近くした場合
に、A.O.は、第6図の線Bで示す如く、再び元
に戻つてくる。したがつて、従来の方法ではA.
O.をあまり負で大きくしないように制御棒を浅
く挿入していたが、この発明の方法では同じA.
O.でも炉心下部近くまで挿入できるわけである。
なお、制御棒バンクのオーバーラツプはそれが僅
かであれば存在しても差支えない。つまり、第6
図に示しているように、従来の方法では制御棒挿
入によるA.O.変化カーブ(図中の線A)のうち、
炉心上部の制御棒を挿入するとA.O.の負の絶対
値が増加する範囲を利用していたのに対し、こ
の発明の方法では、バンクオーバーラツプをなく
して制御バンクを挿入する場合のA.O.変化カー
ブ(図中の線B)のうち炉心下部近傍で制御棒を
挿入するとA.O.の負の絶対値が減少する範囲
を利用することに特徴がある。このため、従来の
方法では不可能であつた軸方向出力分布歪みを起
さずに深く制御棒を挿入することが可能となり、
速い負荷変化能力及び即時全出力復帰能力を持た
せることができる。
First, an important point is that in this invention, when inserting control rods into the reactor core, no bank overlap is provided, and the control rods are inserted in such a way that there is no bank overlap or there is very little bank overlap. . In other words, the axial offset (AO) is an index of the axial power distribution distortion of the core.
is defined as AO = qT - qB/qT + qB x 100 (%), where qT and qB are the outputs of the upper and lower half of the core, respectively. In conventional control rod banks, in order to improve the continuity of reactivity between each bank, each bank is inserted with a certain degree of height, which is called bank overlap, as shown in Figure 5A. There is. That is, in a typical example, the first bank has 128 steps (total steps are 228 steps).
When this happens, the next bank will begin to be inserted at the same time. Therefore, as the control rod is inserted, the axial offset increases more and more toward the negative side as shown by line A in FIG. 6, and does not return to its original state. Therefore, in the conventional method, when the control rod is inserted a certain depth, the AO inevitably becomes large on the negative side, making it difficult to control the power distribution. However, as in the present invention, as shown in FIG. 5B, if the overlap of the control rod banks is eliminated and each bank is inserted independently, when the control rods are nearly fully inserted, the AO will be as shown in FIG. 6. As shown by line B, it returns to the original state again. Therefore, in the conventional method, A.
The control rod was inserted shallowly so as not to make O. too negative, but with the method of this invention the same A.
Even if it is O., it can be inserted almost to the bottom of the reactor core.
Note that there is no problem in the existence of control rod bank overlap as long as it is small. In other words, the 6th
As shown in the figure, in the conventional method, among the AO change curves (line A in the figure) due to control rod insertion,
Whereas the range in which the negative absolute value of AO increases when a control rod is inserted in the upper part of the core, the method of this invention uses the AO change curve when inserting a control bank without bank overlap. It is characterized by utilizing the range (line B in the figure) in which the negative absolute value of AO decreases when a control rod is inserted near the bottom of the core. This makes it possible to insert control rods deeply without causing distortion in the axial power distribution, which was impossible with conventional methods.
It is possible to have quick load change capability and instant full output return capability.

出力減少時にA.O.は炉心平均温度変化により
正側に変化する。このA.O.の変化幅は減速材温
度係数によつて変化するので、炉心寿命によつて
第7図に典型例を示すように変化する。制御棒位
置は、この出力変化によるA.O.の正側への移行
を相殺してA.O.が全出力状態のものからほとん
ど変化しないように炉心下部近傍で動かして決め
られる。
When power decreases, AO changes to the positive side due to changes in core average temperature. Since the range of change in AO changes depending on the temperature coefficient of the moderator, it changes depending on the core life as shown in FIG. 7, a typical example. The control rod position is determined by moving the control rods near the bottom of the core so that the AO shifts to the positive side due to this power change is offset and the AO hardly changes from the full power state.

制御棒ワースは目的の出力変化の出力欠損分に
等価なものが望ましい。例えば、第3図の出力欠
損で100%から50%出力への変化の場合は、必要
な制御棒ワースは約0.7〜1.0%Δρとなる。この例
では約0.8%Δρの制御棒ワースとしておき、寿命
末期近くで制御棒ワースが不足してくる分は他の
制御バンクを炉心上部より挿入して補償し、これ
によりA.O.が負側に歪む分は先の炉心下部にあ
る制御棒バンクをさらに炉心下方に移動して相殺
するようにすればよい。また、多少の反応度の増
減はほう素濃度変化で補償すればよい。このよう
に寿命を通じて標準的な制御棒バンクで出力変化
時の出力欠損に対応できる。
It is desirable that the control rod worth be equivalent to the output loss of the desired output change. For example, in the case of a change in output from 100% to 50% due to the output loss shown in FIG. 3, the required control rod worth is approximately 0.7 to 1.0% Δρ. In this example, the control rod worth is set at approximately 0.8% Δρ, and when the control rod worth becomes insufficient near the end of its life, another control bank is inserted from the top of the core to compensate, and the AO is distorted to the negative side. The control rod bank located at the lower part of the core may be moved further down the core to compensate for this. Further, a slight increase or decrease in reactivity may be compensated for by changing the boron concentration. In this way, the standard control rod bank can cope with power losses during power changes throughout its life.

また、100%から30%出力まで変化する場合な
ど、出力変化幅が変化する場合には、その場合の
出力欠損に相当する制御棒ワースを持つ制御バン
クを標準的に決めておき、各出力変化幅に対応し
てこれらの制御棒バンクを選択すればよい。制御
棒バンクワースは各バンク内の制御棒体数を増減
(例えば9体か5体に減少)すること、または制
御棒1体内の吸収棒本数を増減(例えば20本から
12本に減少)することによつて容易に変えられ
る。
In addition, when the output change range changes, such as when changing from 100% to 30% output, a control bank with a control rod worth corresponding to the output loss in that case is determined as a standard, and each output change These control rod banks can be selected depending on the width. Control rod bankworth can be used to increase or decrease the number of control rods in each bank (from 9 to 5, for example), or to increase or decrease the number of absorption rods in one control rod (from 20 to 5, for example).
(reduced to 12).

〔実施例〕〔Example〕

この例として、100%出力から50%出力へステ
ツプ状に出力降下して50%出力で6時間保つた
後、再びステツプ状に100%出力に出力上昇する
負荷追従の場合の制御棒変化、A.O.変化および
ほう素濃度変化を1次元拡散計算コードで計算し
た例を第8図、第9図に示す。
As an example of this, the control rod changes in the case of load following, in which the output decreases stepwise from 100% output to 50% output, maintains it at 50% output for 6 hours, and then increases the output stepwise again to 100% output, AO Examples of calculations of changes and boron concentration changes using a one-dimensional diffusion calculation code are shown in FIGS. 8 and 9.

第8図は第1サイクル寿命初期における計算例
であり、第9図は第1サイクル寿命末期における
計算例である。それぞれの制御棒ワースが約0.7,
0.8%Δρの例である。軸方向出力分布歪みの指標
であるA.O.が出力変動にかかわらずほぼ定常値
近くに保たれていることがわかる。また、制御棒
はかなり深く挿入されているのでこれを引抜けば
即時復帰能力があることになる。ほう素濃度はキ
セノン変化に対応したカーブになつていることも
わかる。また、これらの図から制御棒は全挿入ま
でまだかなりの余裕があるので他の制御バンクを
さらに炉心上部より挿入し、A.O.の負側の移行
は先の制御バンクを炉心下方にさらに挿入して相
殺すれば、出力欠損の多少の増減は吸収できる余
裕のあることもわかる。
FIG. 8 is an example of calculation at the beginning of the first cycle life, and FIG. 9 is an example of calculation at the end of the first cycle life. Each control rod worth is approximately 0.7,
This is an example of 0.8%Δρ. It can be seen that AO, which is an index of axial power distribution distortion, is maintained close to a steady value regardless of output fluctuations. Also, since the control rods are inserted quite deeply, they have the ability to return immediately if they are pulled out. It can also be seen that the boron concentration forms a curve that corresponds to changes in xenon. Also, from these figures, there is still quite a bit of room for the control rods to be fully inserted, so the other control banks should be further inserted from the top of the core, and for the transition to the negative side of AO, the previous control bank should be further inserted below the core. It can be seen that there is enough room to absorb some increase or decrease in the output deficit if they are offset.

以上の説明から明らかな通り、この発明によれ
ば、制御棒バンクオーバーラツプなしに若しくは
バンクオーバーラツプが小さい状態で所要出力欠
損にほぼ等価のワースを持つ制御棒を炉心下部近
傍に挿入しアキシヤルオフセツトを挿入前のもの
とほぼ同じに保つことにより軸方向出力分布歪み
を起さずに速い負荷変化ができ、かつ、即時復帰
能力もある負荷追従運転ができる加圧水型原子炉
の負荷追従運転方法を得ることができる。
As is clear from the above description, according to the present invention, control rods having a force approximately equivalent to the required power loss are inserted near the bottom of the core without control rod bank overlap or with small bank overlap. By keeping the axial offset almost the same as before insertion, rapid load changes can be made without distorting the axial power distribution, and load following operation with immediate recovery capability is possible. A follow-up driving method can be obtained.

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

第1図は出力変動時の反応度変化の内訳例を示
すグラフ、第2図は出力欠損の出力レベルによる
変化例を示すグラフ、第3図は出力欠損の寿命に
よる変化例を示すグラフ、第4図は従来の運転方
法における出力変動時の制御棒挿入度及びほう素
濃度の変化例を示すグラフ、第5図は制御棒バン
ク挿入例を示すグラフ、第6図は制御棒挿入時の
アキシヤルオフセツト変化例を示すグラフ、第7
図は出力変化に伴うアキシヤルオフセツト変化例
を示すグラフ、第8図は第1サイクル寿命初期の
負荷追従運転時の諸元の計算例を示すグラフ、及
び第9図は第1サイクル寿命末期の負荷追従運転
時の諸元の計算例を示すグラフである。
Figure 1 is a graph showing an example of the breakdown of reactivity changes during output fluctuations, Figure 2 is a graph showing an example of changes in output loss due to output level, Figure 3 is a graph showing an example of changes in output loss due to lifespan, Figure 4 is a graph showing an example of changes in control rod insertion degree and boron concentration during output fluctuations in a conventional operation method, Figure 5 is a graph showing an example of control rod bank insertion, and Figure 6 is a graph showing an example of control rod insertion degree and boron concentration changes during output fluctuations in a conventional operation method. Graph showing examples of changes in shear offset, No. 7
The figure is a graph showing an example of axial offset change due to output change, Figure 8 is a graph showing an example of calculation of specifications during load following operation at the beginning of the first cycle life, and Figure 9 is a graph at the end of the first cycle life. 3 is a graph showing an example of calculation of specifications during load following operation.

Claims (1)

【特許請求の範囲】[Claims] 1 加圧水型原子炉の負荷追従運転における出力
変化による反応度変化分にほぼ等価な制御棒価値
を有する制御棒バンクをバンクオーバーラツプが
無いか若しくはバンクオーバーラツプが小さい状
態で炉心に挿入し、出力低下を急速に行いその後
のキセノン増加による反応度減少はほう素濃度変
化により補償し、その後の出力上昇にあたつては
制御棒引抜により出力変化による反応度変化分を
補償し、出力上昇後のキセノン減少による反応度
増加はほう素濃度変化により補償する運転方法に
おいて、制御棒挿入によるアキシヤルオフセツト
変化のカーブが負側の最大値を越えて更に制御棒
を挿入するとアキシヤルオフセツトの絶対値が減
少する範囲である炉心下部近傍を制御棒の操作範
囲とすることを特徴とする加圧水型原子炉の負荷
追従運転方法。
1. A control rod bank with a control rod value approximately equivalent to the change in reactivity due to a change in output during load following operation of a pressurized water reactor is inserted into the core with no bank overlap or with small bank overlap. , the output is rapidly decreased, and the subsequent decrease in reactivity due to the increase in xenon is compensated for by the change in boron concentration, and when the output is subsequently increased, the change in reactivity due to the output change is compensated for by withdrawing the control rod, and the output is increased. In an operating method in which the increase in reactivity due to the subsequent decrease in xenon is compensated for by changes in boron concentration, if the curve of axial offset change due to control rod insertion exceeds the maximum value on the negative side, and further control rods are inserted, the axial offset will increase. A method of load following operation of a pressurized water reactor, characterized in that the operating range of control rods is set near the lower part of the reactor core, which is the range in which the absolute value of decreases.
JP56004606A 1981-01-17 1981-01-17 Method of operating and following up pwr type reactor Granted JPS57119297A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56004606A JPS57119297A (en) 1981-01-17 1981-01-17 Method of operating and following up pwr type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56004606A JPS57119297A (en) 1981-01-17 1981-01-17 Method of operating and following up pwr type reactor

Publications (2)

Publication Number Publication Date
JPS57119297A JPS57119297A (en) 1982-07-24
JPH027436B2 true JPH027436B2 (en) 1990-02-19

Family

ID=11588696

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56004606A Granted JPS57119297A (en) 1981-01-17 1981-01-17 Method of operating and following up pwr type reactor

Country Status (1)

Country Link
JP (1) JPS57119297A (en)

Also Published As

Publication number Publication date
JPS57119297A (en) 1982-07-24

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