Deprecated: The each() function is deprecated. This message will be suppressed on further calls in /home/zhenxiangba/zhenxiangba.com/public_html/phproxy-improved-master/index.php on line 456
JPH021276B2 - - Google Patents
[go: Go Back, main page]

JPH021276B2 - - Google Patents

Info

Publication number
JPH021276B2
JPH021276B2 JP56018016A JP1801681A JPH021276B2 JP H021276 B2 JPH021276 B2 JP H021276B2 JP 56018016 A JP56018016 A JP 56018016A JP 1801681 A JP1801681 A JP 1801681A JP H021276 B2 JPH021276 B2 JP H021276B2
Authority
JP
Japan
Prior art keywords
output
control rod
boron concentration
change
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 - Lifetime
Application number
JP56018016A
Other languages
Japanese (ja)
Other versions
JPS57133395A (en
Inventor
Hiroshi Tochihara
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 JP56018016A priority Critical patent/JPS57133395A/en
Publication of JPS57133395A publication Critical patent/JPS57133395A/en
Publication of JPH021276B2 publication Critical patent/JPH021276B2/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

Landscapes

  • 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(PWR)の負荷追
従運転方法に関するもので、特にほう素濃度変化
幅及び排出水量を小とする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 reactor (PWR), and particularly to a load following operation method for reducing the range of change in boron concentration and the amount of discharged water.

従来、加圧水型原子炉の反応度制御は制御棒の
挿入、引抜き及びほう素濃度変化によつて行つて
いる。制御棒による制御は速い反応度変化ができ
るが、炉心上部から制御棒を挿入するので、挿入
に従がい軸方向出力分布が歪んでくるという問題
がある。一方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るもので、軸方向出力分布
の問題はないが、大量の水を取扱わなければなら
ないので、反応度変化が遅いという問題点があ
る。
Conventionally, the reactivity of pressurized water reactors has been controlled by inserting and withdrawing control rods and changing boron concentration. Control using control rods allows rapid reactivity changes, but since the control rods are inserted from the top of the core, there is a problem that the axial power distribution becomes distorted as the rods are inserted. On the other hand, the boron concentration variable system increases or decreases the boron concentration in the primary coolant, and there is no problem with the axial output distribution, but the problem is that the reactivity changes slowly because a large amount of water must be handled. There is.

負荷追従運転のように、炉心の出力変動がある
場合の反応度変化について見ると、第1A図に線
1で示すような出力レベル変化があつた場合、反
応度変化は出力レベル変化に伴なう第1B図の実
線2で示すような反応度変化(これを出力欠損分
という)及び点線3で示すようなキセノン(Xe)
変化による反応度変化の2つから成立つている。
そして出力欠損は第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
欠損すなわち図に1点鎖線4で示すものと、1次
冷却材の炉心平均温度変化による図中点線5で示
す出力欠損分との合計、図中実線6で示すように
なる。
Looking at the change in reactivity when there is a fluctuation in the core output, such as during load following operation, if there is a change in the output level as shown by line 1 in Figure 1A, the change in reactivity will be due to the change in the output level. The change in reactivity as shown by the solid line 2 in Figure 1B (this is called the output deficit) and the change in xenon (Xe) as shown by the dotted line 3
It consists of two factors: change in reactivity due to change.
As shown in Figure 2, a typical example of power loss is the power loss due to the Doppler effect due to changes in fuel temperature, which is indicated by the dashed line 4 in the figure, and the power loss due to changes in the core average temperature of the primary coolant. The sum total with the output loss shown by the dotted line 5 becomes as shown by the solid line 6 in the figure.

ドツプラー効果の出力欠損の方は炉心の寿命中
余り変化しないが、温度変化の出力欠損の方は寿
命末期になるに従つて大きくなるので、全体の出
力欠損は第3図に実線7で典型例を示すように、
寿命末期で大きくなつてくる。
The power loss due to the Doppler effect does not change much during the life of the core, but the power loss due to temperature changes increases towards the end of the life, so the overall power loss is shown as a typical example by the solid line 7 in Figure 3. As shown,
It grows larger towards the end of life.

出力変動中の反応度変化のうち、出力欠損分は
制御棒の挿入、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こと
になる。
Among reactivity changes during output fluctuations, if the output loss is compensated for by inserting and withdrawing control rods, rapid output changes can be accommodated, and the Xe change is a slow change, so boron concentration changes can You just have to deal with it.

しかし、100%から50%出力への変化では、出
力欠損は約0.7%△ρ程度であり、一方制御に通
常使われている制御棒バンクDは全挿入で約1.0
〜1.4%△ρ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
大きく歪んで来ることは先にも記載した通りで、
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の歪みを避
けるために、最近では、制御棒を余り深く挿入し
ないで出力変動を行うことが、標準的運転方法と
なつている。
However, when changing from 100% to 50% output, the output loss is about 0.7%△ρ, while control rod bank D, which is normally used for control, is about 1.0% with full insertion.
Since there is a control rod worth of ~1.4%Δρ, if we try to compensate for the power loss with the control rods alone, we need to insert the control rods deep below the center of the reactor core. As mentioned earlier, if the control rod is inserted deeply, the axial power distribution will be greatly distorted.
After that, output distribution fluctuations due to Xe started to occur, which became a problem. In order to avoid such distortions in the axial power distribution, it has recently become a standard operating method to perform power fluctuations without inserting the control rods too deeply.

標準的な負荷追従運転中の出力レベル変化を第
4A図に、制御棒挿入度を第4B図に、ほう素濃
度変化を第4C図にそれぞれ示し、図中線1で示
す出力変化がある場合、制御棒は第4B図の線8
で示すようにその挿入度が変化し、これに伴な
い、第4C図に曲線9で示すほう素濃度変化は出
力欠損分とXe分が混在した形で、複雑な曲線と
なる。また、この例ではほう素濃度変化幅は約
90PPm程度もあり、毎日このような負荷追従運
転を行なうとすると、1日当り約90PPmのほう
素希釈が必要となる。ほう素は1次冷却材全量中
に混入されているので、ほう素希釈を行なうため
には1次冷却材水を排出し、代わりに純水を注入
することが必要となる。運転中のほう素濃度は、
寿命初期の約1000PPmから寿命末期の約100PPm
まで炉心の燃焼と共に単調に減少する。このた
め、寿命末期に近くなり、ほう素濃度が小さくな
ると、ほう素希釈のためには大量の排出水を外に
出して処理することが必要となる。すなわち排出
水及び排出放射能物質が増大するという問題が生
ずる。従つて、実際の負荷追従運転では、この排
出水の処理能力の点から、寿命末期近くでの運転
が制約されることになる。また寿命末期近くでは
当然単位時間当りのほう素濃度希釈速度にも制約
が生じてくるので、この点からも、第4C図の曲
線9で示すような急激なほう素濃度変化はできな
いようになる。
Figure 4A shows the output level change during standard load following operation, Figure 4B shows the control rod insertion degree, and Figure 4C shows the boron concentration change, and when there is an output change shown by line 1 in the figure. , the control rod is line 8 in Figure 4B.
As shown in FIG. 4C, the degree of insertion changes, and as a result, the change in boron concentration shown by curve 9 in FIG. 4C becomes a complex curve in which the output loss and the Xe component are mixed. Also, in this example, the boron concentration change width is approximately
It is about 90PPm, and if such load following operation is performed every day, approximately 90PPm of boron dilution is required per day. Since boron is mixed in the entire amount of the primary coolant, in order to dilute the boron, it is necessary to drain the primary coolant water and inject pure water in its place. The boron concentration during operation is
Approximately 1000PPm at the beginning of life to approximately 100PPm at the end of life
It decreases monotonically as the core burns up to. For this reason, when the product nears the end of its life and the boron concentration decreases, it becomes necessary to discharge a large amount of waste water to the outside for treatment in order to dilute the boron. In other words, a problem arises in that the amount of discharged water and discharged radioactive substances increases. Therefore, in actual load following operation, operation near the end of life is restricted due to the processing capacity of this waste water. In addition, near the end of life, there are naturally restrictions on the boron concentration dilution rate per unit time, so from this point as well, it is impossible to make a rapid change in boron concentration as shown by curve 9 in Figure 4C. .

ほう素濃度変化における以上のような問題点を
解決するために、負荷追従運転中のほう素濃度変
化を極力小さいものにし、排出水量を少なくする
運転方法を提供することがこの発明の目的であ
る。この目的を達成するために、この発明による
負荷追従運転方法は、ほう素濃度変化を減らした
分の反応度変化は制御棒で補償するが、制御棒で
反応度変化を補償するためには、正の反応度が添
加されると制御棒を炉心中に挿入し、負の反応度
が添加されると制御棒を炉心から引き抜く。即
ち、主として制御棒で反応度補償をすると、炉心
中での制御棒の挿入及び引き抜きによる移動が多
くなる。また、制御棒が炉心中に深く挿入される
と軸方向出力分布は炉心下部に歪み、制御棒を炉
心より引き抜くと平坦な軸方向出力分布に戻つて
くる。制御棒が従来の方法よりも多く移動するこ
とになると、軸方向出力分布制御が困難となるの
で、出力上昇前の制御棒の位置を調整し、かつ段
階的に全出力まで出力上昇することによつて、軸
方向出力分布制御を大きな歪なしに行なうことを
特徴としている。
In order to solve the above-mentioned problems with changes in boron concentration, it is an object of the present invention to provide an operating method that minimizes changes in boron concentration during load following operation and reduces the amount of discharged water. . In order to achieve this objective, the load following operation method according to the present invention uses control rods to compensate for reactivity changes by reducing boron concentration changes, but in order to compensate for reactivity changes with control rods, When a positive reactivity is added, the control rod is inserted into the core, and when a negative reactivity is added, the control rod is withdrawn from the core. That is, if reactivity compensation is performed primarily using control rods, the control rods will be moved more often by insertion and withdrawal in the reactor core. Furthermore, when a control rod is deeply inserted into the reactor core, the axial power distribution is distorted toward the lower part of the core, and when the control rod is withdrawn from the core, it returns to a flat axial power distribution. If the control rods move more than in the conventional method, it becomes difficult to control the axial power distribution, so we decided to adjust the position of the control rods before the output rises and gradually increase the output to full output. Therefore, it is characterized in that axial power distribution control can be performed without significant distortion.

従来の運転方法では、ほう素濃度変化幅を縮小
しようとすると、制御棒挿入及び引抜が多くな
り、軸方向出力分布制御が難しくなる。この発明
においては、出力低下時及びその後数時間内の
Xe増加時にも反応度補償は全て制御棒自動制御
で行ない、ほう素濃度変化をさせない。さらに制
御棒が引抜かれて、約20%〜25%挿入度になり、
アキシヤル・オフセツト(A.φ.)が全出力での
定常値−(5%〜10%)程度に近付いて来たら、
必要に応じてほう素希釈をして、制御棒をその位
置に保持する。ここで、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.φ.)
は、qT、qBをそれぞれ炉心上半部及び下半部の出
力とすると、 A.φ.=qT−qB/qT+qB×100(%) で定義される。出力上昇にはまず制御棒を全引抜
にして可能なところまで出力上昇させ、この出力
レベルで数時間保ち、この間のXe減少による反
応度補償は制御棒を挿入して行なう。再び制御棒
を全引抜にして出力上昇し、この出力レベルで数
時間保ち、制御棒挿入でXe分を補償する。この
手順を繰返して全出力まで達する。通常は約3〜
4時間で全出力に復帰できる。このようなやり方
で全出力に復帰した後の軸方向出力分布は、大き
な振動も起こらず容易に制御できる。
In the conventional operating method, when attempting to reduce the boron concentration variation range, control rods are inserted and withdrawn frequently, making it difficult to control the axial power distribution. In this invention, when the output decreases and within several hours thereafter,
Even when Xe increases, all reactivity compensation is performed by automatic control rod control, so that the boron concentration does not change. The control rod is further withdrawn and the insertion degree is about 20% to 25%,
When the axial offset (A.φ.) approaches the steady value - (5% to 10%) at full output,
Dilute the boron as needed to hold the control rod in place. Here, the axial offset (A.φ.) is an index of the axial power distribution distortion of the core.
is defined as A.φ.=q T −q B /q T +q B ×100 (%), where q T and q B are the outputs of the upper and lower half of the core, respectively. To increase the output, first, the control rods are fully withdrawn to increase the output as much as possible, and this output level is maintained for several hours. During this time, the reactivity due to the decrease in Xe is compensated for by inserting the control rods. The control rods are fully withdrawn again to increase the output, maintain this output level for several hours, and then insert the control rods to compensate for the Xe. Repeat this procedure to reach full power. Usually about 3~
Full power can be restored in 4 hours. In this manner, the axial power distribution after returning to full power can be easily controlled without causing large vibrations.

第5A〜5C図はこの発明による運転方法の場
合を例示したもので、出力レベル変化を第5A図
の線10で、制御棒挿入度を第5B図の線11
で、ほう素濃度変化を第5C図の曲線12でそれ
ぞれ時間に対して示している。第5B図の線11
で示すように、制御棒移動が多く、第5C図の曲
線12が示すように、ほう素濃度変化幅は従来方
法による点線9で示すもの(第4C図の曲線9と
同じ)に比べて、約半分以下に小さくなつてお
り、排出水量もこれに比例して減少することが理
解されるであろう。
5A to 5C illustrate the case of the operating method according to the present invention, in which the output level change is indicated by line 10 in FIG. 5A, and the control rod insertion degree is indicated by line 11 in FIG. 5B.
The change in boron concentration is shown by curve 12 in FIG. 5C with respect to time. Line 11 in Figure 5B
As shown in FIG. 5C, the control rod movement is large, and as shown by curve 12 in FIG. 5C, the boron concentration change range is greater than that shown by dotted line 9 in the conventional method (same as curve 9 in FIG. 4C). It will be understood that the size has been reduced by about half or less, and the amount of discharged water has been reduced in proportion to this.

また、第5A図の線10に示すように、出力低
下時には、制御棒でステツプ状に出力低下ができ
るので、低出力で6時間維持するパターンで、従
来のものよりも全出力復帰までの時間を短かくで
きる。出力上昇のところは段階的に出力上昇して
行くので、線出力上昇からの燃料棒健全性が悪化
されることもない。また制御棒自動制御運転だけ
で行なえる運転範囲が広くなりほう素濃度変更操
作も減少してくるので、運転操作が容易になる。
In addition, as shown by line 10 in Figure 5A, when the output decreases, the control rod can reduce the output in steps, so the pattern of maintaining the low output for 6 hours takes longer than the conventional method to return to full output. can be made shorter. Since the output increases step by step, the health of the fuel rods will not deteriorate as the linear output increases. In addition, the operating range that can be performed only by automatic control rod operation becomes wider, and the number of boron concentration changing operations is reduced, making operation easier.

第3図の線7に見られるように、寿命末期にな
ると出力欠損が大きくなつてくるため、出力低下
時に挿入される制御棒も深くなり、これを引抜い
てその後のXe増加に全て対応することが可能と
なる。この関係は第6図に例示するように、出力
低下時に挿入される制御棒反応度、即ち出力変化
に相当する出力欠損と出力低下後のキセノン増加
による反応度変化とをほう素濃度変化に換算して
示している。第6図中の実線13,14は夫々寿
命初期及び末期における出力低下後6時間目まで
のキセノン反応度変化に相当するほう素濃度変化
を表わし、また、点線15,16は夫々寿命初期
および末期において制御棒挿入により得られる出
力欠損相当のほう素濃度変化に換算して表わして
いる。即ち点線15,16は寿命初期および末期
において制御棒を引抜くことにより得られる正の
反応度を表わしているので、実線が点線より下側
にある出力変化巾領域では、出力低下時およびそ
の後の低出力レベルでのキセノン反応度変化はほ
う素濃度変化によらず全て制御棒引抜で対応でき
ることを示している。寿命初期においては実線1
3が点線15より下側にある範囲A、又寿命末期
においては実線14がほぼ全出力変化巾にわたつ
て点線16より下側にある範囲で制御棒操作によ
りキセノン反応度を補償できることを示してい
る。
As can be seen from line 7 in Figure 3, the output loss increases at the end of the life, so the control rod inserted when the output decreases also becomes deeper, and it is necessary to pull it out to cope with the subsequent increase in Xe. becomes possible. As illustrated in Figure 6, this relationship is expressed by converting the reactivity of the control rods inserted when the output is reduced, that is, the output loss corresponding to the output change and the reactivity change due to the increase in xenon after the output decrease, into a boron concentration change. It is shown as follows. Solid lines 13 and 14 in FIG. 6 represent changes in boron concentration corresponding to changes in xenon reactivity up to 6 hours after power reduction at the beginning and end of life, respectively, and dotted lines 15 and 16 represent changes in boron concentration at the beginning and end of life, respectively. It is expressed in terms of the boron concentration change equivalent to the output loss obtained by inserting the control rod. In other words, the dotted lines 15 and 16 represent the positive reactivity obtained by withdrawing the control rod at the beginning and end of its life, so in the output change range where the solid line is below the dotted line, it This shows that changes in xenon reactivity at low power levels can be dealt with by withdrawing the control rod, regardless of changes in boron concentration. At the beginning of life, solid line 1
3 is below the dotted line 15, and in the range A where the solid line 14 is below the dotted line 16 over almost the entire output change range at the end of the life, the xenon reactivity can be compensated by control rod operation. There is.

従つて、寿命末期近くでは出力低下、その後の
低出力レベル及び出力上昇時ではほぼ制御棒自動
制御運転だけでカバーでき、ほう素濃度変化は不
要となる。この場合はほう素濃度変化が必要なの
は、出力上昇後のXeオーバーシユートによる僅
かな部分のみであるため、寿命末期まで、負荷追
従運転を続けることが可能となる。
Therefore, near the end of the life, the output decreases, and the subsequent low output level and output increase can be covered by automatic control rod operation alone, and boron concentration changes are not required. In this case, the boron concentration needs to be changed only to a small extent due to Xe overshoot after the output increases, so it is possible to continue load following operation until the end of the life.

この発明の運転方法によれば、ほう素濃度変化
をあまり大きくせず、全出力での軸方向出力分布
も歪ませずに負荷追従運転が可能である。1例と
して、第1サイクル寿命初期及び寿命末期におい
て、100%出力から50%出力にステツプ状に出力
低下し、50%出力で6時間保つた後、段階的に全
出力に復帰する負荷追従運転について、電子計算
機を使用して1次元拡散コードで計算した例を、
寿命初期の例を第7A〜7D図、寿命末期を第8
A−8D図に示す。計算上の簡略化のために、制
御棒移動は連続的に行わず、30分間隔程度にまと
めているため、第7C及び8C図の線19,24
で示すA・φ・及び第7D及び8D図に線21,
26で示すほう素濃度変化の曲線がぎざぎざにな
つているが、実際にはこれらの曲線の平均値をと
おることになる。なお、図中線17,22が出力
レベル、線18,23が制御棒挿入度、線20,
25が全出力での定常値を示している。第7C及
び第8C図の線19,24に示すA・φ・は全出
力復帰後、定常的な値に戻り、Xe振動などは起
らないこと、及び第7D及び8D図の曲線21,
26で示すように、ほう素濃度変化幅は従来のも
の(第4C図線9)より、約半分以下に縮小され
ていることがわかる。制御棒の動き方も寿命初
期、末期も似たようなものであり、出力低下後2
〜3時間で約25%挿入に保持すればよい。
According to the operating method of the present invention, load following operation is possible without making the boron concentration change too large and without distorting the axial output distribution at full output. As an example, at the beginning of the first cycle life and at the end of life, the output is reduced stepwise from 100% output to 50% output, maintained at 50% output for 6 hours, and then returned to full output in stages. An example of calculation using a one-dimensional diffusion code using an electronic computer is as follows.
Examples at the beginning of life are shown in Figures 7A to 7D, and examples at the end of life are shown in Figure 8.
Shown in Figure A-8D. To simplify calculations, the control rods are not moved continuously but at intervals of about 30 minutes, so lines 19 and 24 in Figures 7C and 8C
A・φ・ shown by and line 21 in Figures 7D and 8D,
Although the boron concentration change curve indicated by 26 is jagged, it actually passes through the average value of these curves. In addition, lines 17 and 22 in the figure indicate the output level, lines 18 and 23 indicate the control rod insertion degree, and lines 20 and 22 indicate the control rod insertion degree.
25 indicates the steady value at full output. A・φ・ shown by lines 19 and 24 in FIGS. 7C and 8C returns to a steady value after the full output is restored, and Xe vibration does not occur, and curves 21 and 24 in FIGS. 7D and 8D
As shown by 26, it can be seen that the boron concentration change width is reduced to about half or less compared to the conventional one (line 9 in Fig. 4C). The movement of the control rods is similar at the beginning and end of their life, and after the output decreases
It may be maintained at approximately 25% insertion for ~3 hours.

以上のように、この発明の負荷追従運転方法に
よれば、従来の方法の欠点であつた寿命末期での
負荷追従運転制約を解消することができ、ほう素
濃度変化幅が従来のものより大幅に縮小されるの
で、1次冷却材からの排水量を大幅に低下させる
ことができ、排出水の処理操作を減らし、かつ制
御棒自動運転範囲を拡大して、負荷追従運転中の
運転性を大幅に向上させることができる。
As described above, according to the load following operation method of the present invention, it is possible to eliminate the load following operation restriction at the end of life, which was a drawback of the conventional method, and the boron concentration change range is much larger than that of the conventional method. Since the amount of water discharged from the primary coolant can be significantly reduced, the amount of water discharged from the primary coolant can be reduced, the amount of wastewater treatment operations can be reduced, and the control rod automatic operation range can be expanded, greatly improving operability during load following operation. can be improved.

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

第1A図は負荷追従運転における出力レベルの
時間に伴なう変化の1例を示す線図、第1B図は
第1A図の出力レベル変化に伴なう反応度変化を
示す線図、第2図は出力レベルに対する出力欠損
を示す線図、第3図は炉心寿命に対する出力欠損
を示す線図、第4A図は標準的な負荷追従運転中
の時間対出力レベル変化を示す線図、第4B図は
制御棒挿入度、第4C図はほう素濃度変化を示す
線図、第5A図はこの発明による運転方法の場合
の出力レベル変化、第5B図は制御棒挿入度、第
5C図はほう素濃度変化をそれぞれ示す線図、第
6図はほう素濃度変化と出力欠損との関係を示す
線図、第7A図及び第8A図はそれぞれ寿命初期
及び末期のこの発明による負荷追従運転の計算例
を示す出力レベルの線図、第7B、図第8B図は
制御棒挿入度を第7C及び8C図はアキシヤルオ
フセツト(A・φ・)を第7D及び8D図はほう
素濃度変化をそれぞれ示す線図である。 図中、1,10,17,22……出力レベルを
示す線、2……出力欠損分、3……Xe変化分、
4,5,6……出力欠損、7……炉心寿命に対す
る出力欠損、8……制御棒挿入後を示す実線、9
……ほう素濃度変化を示す曲線、11……この発
明による制御棒挿入度を示す線、12……この発
明によるほう素濃度変化を示す曲線。
Figure 1A is a diagram showing an example of changes in output level over time during load following operation, Figure 1B is a diagram showing changes in reactivity accompanying changes in output level in Figure 1A, and Figure 2 Figure 3 is a diagram showing power loss versus power level, Figure 3 is a diagram showing power loss versus core life, Figure 4A is a diagram showing power level change versus time during standard load following operation, and Figure 4B is a diagram showing power loss versus time during standard load following operation. The figure shows the degree of control rod insertion, Figure 4C shows the change in boron concentration, Figure 5A shows the change in output level in the case of the operating method according to the present invention, Figure 5B shows the degree of control rod insertion, and Figure 5C shows the change in boron concentration. Figure 6 is a diagram showing the relationship between boron concentration change and output loss, and Figures 7A and 8A are calculations of load following operation according to the present invention at the beginning and end of life, respectively. Output level diagrams showing examples, Figures 7B and 8B show the control rod insertion degree, Figures 7C and 8C show the axial offset (A・φ・), and Figures 7D and 8D show the change in boron concentration. They are line diagrams shown respectively. In the figure, 1, 10, 17, 22... Lines indicating output level, 2... Output loss, 3... Xe change,
4, 5, 6... Output loss, 7... Output loss relative to core life, 8... Solid line showing after control rod insertion, 9
...Curve showing changes in boron concentration, 11...Line showing control rod insertion degree according to the present invention, 12...Curve showing changes in boron concentration according to the present invention.

Claims (1)

【特許請求の範囲】[Claims] 1 炉心への制御棒挿入により出力低下を急速に
行ないその後のキセノン増加による反応度減少は
制御棒を引抜いて補償し、制御棒が約20〜25%挿
入程度に達しアキシヤルオフセツトが全出力の定
常値より約5〜10%程度負側に達した後は、ほう
素濃度変化による制御で制御棒はその位置に保持
し、その後の出力上昇にあたつては制御棒引抜に
よりステツプ状に出力上昇させ、出力上昇後のキ
セノン減少による反応度増加を制御棒の再挿入に
より補償し、数時間経過後再び制御棒を引抜いて
ステツプ状に出力上昇し、全出力に達するまでこ
れを繰返すことを特徴とする負荷追従運転方法。
1 The power is rapidly reduced by inserting the control rods into the reactor core, and the subsequent decrease in reactivity due to the increase in xenon is compensated for by withdrawing the control rods, and when the control rods reach approximately 20-25% insertion, the axial offset reaches full power. After reaching a negative side of about 5 to 10% from the steady value, the control rod is held in that position by control based on changes in boron concentration, and when the output increases thereafter, the control rod is pulled out in a step-like manner. Increase the output, compensate for the increase in reactivity due to the decrease in xenon after the increase in output by reinserting the control rod, and after several hours have elapsed, pull out the control rod again and increase the output in steps, repeating this until the full output is reached. A load following operation method characterized by:
JP56018016A 1981-02-12 1981-02-12 Following-up operation method Granted JPS57133395A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56018016A JPS57133395A (en) 1981-02-12 1981-02-12 Following-up operation method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56018016A JPS57133395A (en) 1981-02-12 1981-02-12 Following-up operation method

Publications (2)

Publication Number Publication Date
JPS57133395A JPS57133395A (en) 1982-08-18
JPH021276B2 true JPH021276B2 (en) 1990-01-10

Family

ID=11959866

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56018016A Granted JPS57133395A (en) 1981-02-12 1981-02-12 Following-up operation method

Country Status (1)

Country Link
JP (1) JPS57133395A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP4073821B1 (en) * 2019-12-12 2024-03-20 Framatome GmbH Method for controlling a nuclear power plant and controller

Also Published As

Publication number Publication date
JPS57133395A (en) 1982-08-18

Similar Documents

Publication Publication Date Title
JPS5829878B2 (en) fuel assembly
JPH021276B2 (en)
JPS6129478B2 (en)
EP0103249B1 (en) Operating method of boiling water reactor
JPH05240984A (en) Method and apparatus for controlling a nuclear reactor so that adjustment of boron concentration during load changes is minimized
JPH027436B2 (en)
JPH0457999B2 (en)
JPS6318151B2 (en)
JP2868894B2 (en) How to monitor nuclear power plants
JP3117207B2 (en) Fuel assembly for boiling water reactor
JP2026030282A (en) Control rod pattern and withdrawal sequence selection device, and automatic power adjustment device equipped with the same
JPH047839B2 (en)
JPH0631819B2 (en) Load following operation method of nuclear power plant
JPH0439639B2 (en)
JPS61259194A (en) Starting operation method of nuclear reactor
JPH0198992A (en) Fuel assembly for boiling water type nuclear reactor
JPS6325594A (en) Method of operating nuclear reactor
JP3053226B2 (en) Selection control rod insertion method
JP3021684B2 (en) Start-up operation of boiling water reactor
JPH10282281A (en) Operating method of boiling water reactor
JPH0241714B2 (en)
JPS63171390A (en) Method of operating nuclear reactor
JPH04235386A (en) Operating method of reactor
JPH0381693A (en) Control method for nuclear reactor control rod
JPS58155396A (en) Load following-up method of bwr type power plant