JPH024875B2 - - Google Patents
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- Publication number
- JPH024875B2 JPH024875B2 JP55026580A JP2658080A JPH024875B2 JP H024875 B2 JPH024875 B2 JP H024875B2 JP 55026580 A JP55026580 A JP 55026580A JP 2658080 A JP2658080 A JP 2658080A JP H024875 B2 JPH024875 B2 JP H024875B2
- Authority
- JP
- Japan
- Prior art keywords
- core
- control rod
- reactor
- control
- control rods
- 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
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Classifications
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- 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
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- 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(BWR)の運転方
法に係り、特に原子炉の起動及びパタン交換等の
出力変更運転制御に好適な沸騰水型原子炉の運転
方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method of operating a boiling water reactor (BWR), and in particular, a method of operating a boiling water reactor suitable for reactor startup and output change operation control such as pattern exchange. It is related to.
BWRでは燃料ペレツトと被覆管との相互作用
による燃料棒の破損を防止する観点から制御棒の
引抜きは、燃料棒の線出力密度があるしきい値
(以後、しきい値という)以下、またはその燃料
棒がすでに経験したことのある線出力密度(以
下、エンベロプという)以下で行うように制限さ
れている。更にしきい値またはエンベロプ以上で
の出力上昇は炉心流量の増加によつて行い、その
上昇率も制限されている。 In BWR, from the viewpoint of preventing fuel rod damage due to interaction between fuel pellets and cladding, control rods should be withdrawn only when the linear power density of the fuel rods is below a certain threshold (hereinafter referred to as the threshold) or below. It is limited to operating below the linear power density (hereinafter referred to as envelope) that the fuel rods have already experienced. Furthermore, power increases above a threshold or envelope are achieved by increasing the core flow rate, and the rate of increase is also limited.
上記の運転条件を遵守するため、特開昭54−
129290号公報に示された従来例は、原子炉出力を
最終目標である設定出力まで上昇させる運転途中
でエンベロプを拡張する運転法がとられている。
このエンベロプ拡張ではすべての燃料で一度以上
高出力レベルを経験させる必要があるが、この高
出力レベル実現のための炉心流量制御による出力
上昇率が前記のように制限されているため、長時
間を要している。たとえば、電気出力784MW、
出力密度51KW/l、制御棒引抜きのしきい値
8KW/ft、出力上昇率の制限値0.06KW/ft/h
のBWRの場合、起動所要時間は約21日である。
つまり起動、パタン交換の所要時間は長くなり、
原子炉稼動率の悪化の原因となつている。 In order to comply with the above operating conditions,
In the conventional example disclosed in Japanese Patent No. 129290, an operating method is adopted in which the envelope is expanded during operation to increase the reactor output to the set output, which is the final target.
This envelope expansion requires all fuels to experience a high power level at least once, but since the rate of power increase through core flow control to achieve this high power level is limited as mentioned above, it takes a long time. I need it. For example, electrical output 784MW,
Power density 51KW/l, control rod withdrawal threshold
8KW/ft, output increase rate limit 0.06KW/ft/h
For BWR, the startup time is approximately 21 days.
In other words, the time required for startup and pattern exchange will be longer.
This is a cause of deterioration in reactor operation rate.
本発明の目的は、上記した従来技術の欠点をな
くし、燃料破損をおこさずしかも原子炉稼動率を
向上できる沸騰水型原子炉の運転方法を提供する
ことにある。 SUMMARY OF THE INVENTION An object of the present invention is to provide a method for operating a boiling water reactor that eliminates the drawbacks of the prior art described above, prevents fuel damage, and improves reactor operating efficiency.
本発明の特徴は、目標制御棒パタンに、更に1
本または複数本の制御棒を炉心周辺部に挿入した
制御棒パタンを付加してなる状態での運転が、炉
心流量定格値の50%以下の炉心流量範囲において
のみ行なわれることにある。 The feature of the present invention is that the target control rod pattern further includes one
Operation with a control rod pattern in which one or more control rods are inserted into the periphery of the core is performed only in a core flow rate range of 50% or less of the core flow rate rated value.
本発明は、以下に示す2つの事実を考慮してな
されたものである。第1は、燃料破損が操作制御
棒に隣接した燃料集合体でしかもしきい値または
エンベロプ以上の線出力密度を経験する場合にか
ぎられていることである。これは、特開昭51−
141990号公報の第6図に示されていることからも
明らかである。すなわち引抜かれる制御棒17C
に隣接する燃料集合体29C内のaの位置にある
燃料棒が制御棒17Cの先端付近で曲線33から
曲線34のように大きく変化してその燃料棒の破
損の危険性が著しく大きいのに対して、燃料集合
体29Cに隣接して制御棒17Cよりも若干離れ
ている燃料集合体29Bのbの位置の燃料棒の軸
方向の出力分布は制御棒17Cの引抜きによつて
も曲線32の状態からほとんど変化しなくその燃
料棒の破損の危険性は前述のaの位置の燃料棒の
それよりも著しく小さい。このような事実に基づ
けば、出力ピーキングの大きい領域では制御棒操
作を原子炉出力が低く線出力密度が小さい時点
(制御棒引抜き後も線出力密度がしきい値以下と
なる時点)で行い、その後に、出力ピーキングの
小さい領域で制御棒を引抜いて原子炉出力を増大
させる運転をすればよいことになる。つまりこの
運転法では、出力ピーキングの小さい領域で制御
棒を引抜く場合において後述するように炉心全体
からみれば線出力密度がしきい値を越える燃料集
合体があるが、制御棒操作時にその制御棒に隣接
している燃料集合体では線出力密度をしきい値以
下とすることができ、その結果、燃料破損をなく
すことができる。第2は、炉心周辺部では中性子
のもれが大きいことである。一般に炉心周辺部で
線出力密度は小さくなつておりこれを利用すれ
ば、しきい値以下で制御棒引抜きをすることは容
易である(制御棒操作時における出力ピークは一
般に大きくなるが)。 The present invention was made in consideration of the following two facts. First, fuel failure is limited to fuel assemblies adjacent to operational control rods that experience linear power densities above a threshold or envelope. This is JP-A-51-
This is clear from what is shown in FIG. 6 of Publication No. 141990. In other words, the control rod 17C that is pulled out
The fuel rod at position a in the fuel assembly 29C adjacent to the control rod changes greatly from curve 33 to curve 34 near the tip of the control rod 17C, and the risk of damage to that fuel rod is extremely large. Therefore, the axial power distribution of the fuel rod at position b of the fuel assembly 29B, which is adjacent to the fuel assembly 29C and is slightly farther away than the control rod 17C, remains in the state of curve 32 even when the control rod 17C is withdrawn. The risk of breakage of the fuel rod is significantly smaller than that of the fuel rod in position a described above. Based on these facts, in regions with large power peaking, control rod operations should be performed at a time when the reactor power is low and the linear power density is low (the time when the linear power density remains below the threshold even after control rod withdrawal). After that, the reactor can be operated to increase the reactor output by withdrawing the control rods in a region where the output peaking is small. In other words, in this operating method, when the control rods are withdrawn in a region with small power peaking, there are fuel assemblies whose linear power density exceeds the threshold value from the perspective of the entire reactor core, as will be described later. The linear power density in the fuel assemblies adjacent to the rods can be below a threshold value, thereby eliminating fuel failure. The second problem is that neutron leakage is large around the core. In general, the linear power density is lower around the core, and if this is used, it is easy to pull out the control rods below the threshold (although the power peak when operating the control rods is generally larger).
以上述べた2つの考察にもとづいて、本発明に
なる沸騰水型原子炉の運転方法では、初めに炉心
周辺部に制御棒が挿入されて原子炉出力が小さく
なつている状態で、出力ピーキングが大きい炉心
中央部で制御棒を操作する。つまり、新しい燃料
集合体が炉心内に装荷された後における運転サイ
クルでの最初の起動時には燃料破損を防止するた
めにしきい値以下で、またエンベロプが形成され
た運転サイクル途中での原子炉スクラム後の再起
動時にはエンベロプ以下で、炉心中央部内に挿入
されている制御棒を引抜き、炉心中央部であらか
じめ目標制御棒パタンを実現する。しかる後、線
出力密度が小さい炉心周辺部に挿入されている制
御棒を全部引抜き、原子炉出力を最終目標である
設定レベルまで上昇させることの可能な目標制御
棒パタンを実現する。この一連の制御棒操作時に
おいて、操作される制御棒に隣接した燃料集合体
はしきい値を越えることがない。従つて、燃料健
全性の維持が期待できる。 Based on the above two considerations, in the boiling water reactor operating method according to the present invention, the control rods are first inserted into the periphery of the reactor core and the reactor output is reduced, and then the output peaking is reduced. Control rods are operated in the center of the large reactor core. This means that during the first start-up in the operating cycle after a new fuel assembly is loaded into the core, to prevent fuel failure, and after the reactor scram in the middle of the operating cycle when the envelope has formed. When restarting, the control rods inserted in the center of the reactor core are pulled out below the envelope, and the target control rod pattern is achieved in advance in the center of the reactor core. After that, all the control rods inserted around the core where the linear power density is low are pulled out to realize a target control rod pattern that can increase the reactor power to the final target set level. During this series of control rod operations, the fuel assembly adjacent to the operated control rod does not exceed the threshold value. Therefore, maintenance of fuel integrity can be expected.
以上まとめると、本発明は、目標制御棒パタン
(注目している出力上昇運転で最終的に達成しよ
うとしている制御棒パタン)まで制御棒を引抜く
以前に、その目標制御棒パタンに、更に1本また
は複数本の制御棒を炉心周辺部に挿入した制御棒
パタンを付加した状態での運転を炉心流量定格値
の50%以下の炉心流量範囲でのみ行うものであ
る。 In summary, the present invention provides an additional step to the target control rod pattern before pulling out the control rods to the target control rod pattern (the control rod pattern that is finally being achieved in the output increase operation of interest). Operation with a control rod pattern in which one or more control rods are inserted into the periphery of the core is performed only in a core flow rate range of 50% or less of the core flow rate rated value.
本発明は、炉心周辺部に制御棒を挿入した制御
棒パタンでの運転期間を有する点において、前述
の特開昭54−129290号公報(特願昭53−35492号)
と同じ特徴を有している。しかし、特開昭54−
129290公報に示された発明は、原子炉出力を最終
目標である設定レベルまで上昇させる過程におい
てエンベロプを拡張するために炉心周辺部に制御
棒を挿入した状態で炉心流量を定格値の60%以上
にして運転することが必要不可欠である。これに
対し、本発明は、上記従来例のようにエンベロプ
の拡張を目的としないため、目標制御棒パタンに
制御棒を炉心周辺部に挿入した制御棒パタンを付
加した状態での運転を炉心流量定格値の50%以下
の炉心流量範囲でのみで行うことに特徴がある。
このような本発明は、目標制御棒パタンを形成す
るまでの制御棒引抜き操作を炉心流量定格値の50
%以下の炉心流量範囲でのみ行つており炉心流量
定格値の50%を越える炉心領域では制御棒の引抜
き操作を行つていないので、制御棒の引抜きによ
つて燃料が破損することを防止できる。炉心流量
が定格値の50%以上を越える状態で炉心周辺部の
制御棒を引抜くと、その引抜き制御棒に隣接する
燃料集合体の線出力密度がしきい値を越えそれに
破損が生じる危険性がある。また、本発明は、目
標制御棒パタンに制御棒を炉心周辺部に挿入した
制御棒パタンを付加した状態で炉心流量定格値の
50%を越えて炉心流量を増大させるエンベロプ拡
張のための運転を行う必要がなく、最終目標であ
る設定レベルまで原子炉出力を上昇させるのに必
要な時間を著しく短縮できる。 The present invention has an operation period with a control rod pattern in which control rods are inserted around the core, and is similar to the above-mentioned Japanese Patent Application Laid-Open No. 54-129290 (Japanese Patent Application No. 53-35492).
has the same characteristics. However, JP-A-54-
The invention disclosed in Publication No. 129290 involves increasing the reactor core flow rate to 60% or more of the rated value with control rods inserted around the core in order to expand the envelope in the process of increasing the reactor power to the final target set level. It is essential to drive safely. In contrast, the present invention does not aim at expanding the envelope as in the conventional example, and therefore operates with a control rod pattern in which control rods are inserted into the core periphery added to the target control rod pattern. It is unique in that it is carried out only in the core flow rate range below 50% of the rated value.
In this invention, the control rod withdrawal operation until the target control rod pattern is formed is performed at a rate of 50% of the core flow rate rated value.
% or less, and control rod withdrawal is not performed in the core region where the core flow rate exceeds 50% of the rated value, so it is possible to prevent fuel damage due to control rod withdrawal. . If a control rod around the core is pulled out when the core flow rate exceeds 50% of the rated value, there is a risk that the linear power density of the fuel assembly adjacent to the pulled control rod will exceed the threshold and cause damage. There is. In addition, the present invention provides a method for determining the rated value of the core flow rate when a control rod pattern in which control rods are inserted into the core periphery is added to the target control rod pattern.
There is no need for envelope expansion operations that increase core flow rate by more than 50%, significantly shortening the time required to increase reactor power to the set level, which is the ultimate goal.
本発明の好適な一実施例であるBWRの運転方
法を、従来例と同じ電気出力784MWe、出力密度
51KW/l、制御棒引抜きのしきい値8KW/ft、
出力上昇率の制限値0.06KW/ft/hのBWRに
適用した場合を例にとり説明する。 The operating method of the BWR, which is a preferred embodiment of the present invention, has the same electric output of 784 MWe and power density as the conventional example.
51KW/l, control rod withdrawal threshold 8KW/ft,
An example of application to a BWR with an output increase rate limit of 0.06KW/ft/h will be explained.
原子炉の熱出力と炉心流量とを座標軸とした
BWRの起動運転時の軌跡を第1図に示す。第1
図中、実線は制御棒操作時、破線は炉心流量制御
時における熱出力の上昇過程を示す。代表的な時
点での制御棒パタン(1/4炉心)を第2図に示す。
第2図において制御棒位置に示された数字は制御
棒挿入の割合を示し、24は全挿入を、0または空
白部分は全引抜きをそれぞれ示している。本実施
例の起動時において、制御棒引抜きは最小炉心流
量(炉心流量定格値の約40%)で行う。すなわ
ち、最小炉心流量に保持して炉心周辺部に制御棒
を挿入した状態で出力ピーキングの大きい領域で
ある炉心中央部の制御棒を引抜き第2図aの制御
棒パタンを実現する(第1図の運転点1)。つま
り本実施例では炉心流量40%で炉心周辺部に全挿
入の制御棒を配置した状態で炉心中央部の制御棒
を所定量引抜いているので、線出力密度がしきい
値8KW/ft以下となり燃料破損を生じることな
く炉心中央部で定格出力制御棒パタン(定格出力
を出すための制御棒パタン)を、炉心周辺部で全
挿入の制御棒がある制御棒パタンを実現すること
ができる。第2図aの制御棒パタンは、炉心中央
部の制御棒が周辺部の制御棒よりも引抜かれてい
るパタンである。第2図aの制御棒パタンを形成
する過程における制御棒引抜きにより原子炉の熱
出力は、第1図の実線に沿つて上昇し、第2図a
の制御棒パタンが形成された時の熱出力は第1図
の運転点1の熱出力となる。この後、炉心周辺部
に挿入された制御棒を順次引抜いて第2図bに示
す定格出力制御棒パタンを形成する(第1図の運
転2)。炉心周辺部の制御棒を引抜いて第2図b
の制御棒パタンを形成することによつて、原子炉
の熱出力は第1図の運転点1から実線に沿つて第
1図の運転点2まで上昇する。第3図は、第2図
aの制御棒パタンから炉心周辺部の制御棒を引抜
くときの線出力密度の変化を示している。曲線5
は、炉心周辺部に全挿入されている一本の制御棒
を全挿入から全引抜きまで移動させたときにその
制御棒に隣接している燃料集合体での線出力密度
の変化を示している。曲線4は、炉心周辺部に挿
入されている全制御棒(本実施例では24本の制御
棒)を引抜いたときの炉心中央部において最大の
線出力密度になる燃料集合体における線出力密度
の変化を示している。炉心周辺部の制御棒は炉心
中心に対して点対称になるように1/24ずつ、順番
に引抜かれる。曲線4の黒丸は、炉心周辺部に挿
入されている全制御棒が黒丸に対応する制御棒挿
入量まで引抜かれたときの前述の炉心中央部の燃
料集合体の線出力密度を示している。例えば、第
3図の左から2つ目の黒丸は、炉心周辺部に挿入
されている24本の制御棒がすべて20/24の位置ま
で引抜かれたときの前述の燃料集合体での線出力
密度である。炉心周辺部から引抜かれる制御棒に
隣接した燃料集合体の線出力密度は、前述のよう
に炉心周辺部での中性子のもれが大きいので線出
力密度は小さく制御棒が全引抜きされた状態でも
8KW/ft以下(第3図曲線5)である。このた
め、炉心周辺部に位置すると共に引抜き制御棒に
隣接して制御棒引抜き時における線出力密度の変
化が最も大きい燃料集合体においても、燃料棒の
破損が生じない。しかしながら炉心中央部に存在
する燃料集合体は、第2図aの制御棒パタンから
炉心周辺部の制御棒を引抜くことによつて第3図
の曲線4に示すように線出力密度が8KW/ftを
越えるものが生じる。これは、炉心周辺部に挿入
されている全部の制御棒を全引抜き状態にするま
での線出力密度のトータルの変化量である。炉心
周辺部に挿入されている各制御棒は前述したよう
に炉心中心に対して点対称になるように1本づつ
順番で1/24ずつ引抜かれしかも特開昭51−141990
号公報の第6図に示すように制御棒引抜きの影響
がその制御棒から離れた位置にある燃料集合体に
はあまり及ばないので、炉心中央部に配置された
燃料集合体の線出力密度は炉心周辺部の制御棒の
引抜き操作によつて大幅に増加しない。すなわ
ち、炉心中央部に配置された燃料集合体の線出力
密度は、炉心周辺部の制御棒を引抜いても
0.06KW/ft/h程度の増加率となる。このた
め、炉心周辺部の制御棒を引抜いたとしても、炉
心中央部の燃料集合体に破損が生じない。なお、
炉心周辺部においては、1本の制御棒の所定量の
引抜きが完了した後、キセノンの蓄積を行なうた
めに所定時間経過後に次の制御棒の引抜きを行
う。 The coordinate axes are the thermal output of the reactor and the core flow rate.
Figure 1 shows the trajectory during startup operation of the BWR. 1st
In the figure, the solid line shows the process of increasing thermal output during control rod operation, and the broken line shows the process of increasing thermal output during core flow rate control. Figure 2 shows the control rod pattern (1/4 core) at a typical point in time.
In FIG. 2, the numbers shown at the control rod positions indicate the rate of control rod insertion; 24 indicates full insertion, and 0 or blank space indicates full withdrawal. At startup of this embodiment, control rod withdrawal is performed at the minimum core flow rate (approximately 40% of the core flow rate rated value). That is, with the core flow maintained at the minimum core flow rate and the control rods inserted in the core periphery, the control rods in the center of the core, where the power peaking is large, are pulled out to achieve the control rod pattern shown in Figure 2a (Figure 1). Operating point 1). In other words, in this example, the control rods in the center of the core are withdrawn by a predetermined amount with the core flow rate at 40% and all the control rods inserted in the core periphery, so the linear power density is below the threshold of 8KW/ft. It is possible to realize a rated output control rod pattern (a control rod pattern for producing rated output) in the center of the core without causing fuel damage, and a control rod pattern with fully inserted control rods in the periphery of the core. The control rod pattern shown in FIG. 2a is a pattern in which the control rods in the center of the core are pulled out more than the control rods in the periphery. As the control rods are withdrawn in the process of forming the control rod pattern shown in Figure 2a, the thermal output of the reactor increases along the solid line in Figure 1;
The thermal output when the control rod pattern is formed is the thermal output at operating point 1 in FIG. Thereafter, the control rods inserted into the periphery of the core are sequentially pulled out to form the rated output control rod pattern shown in FIG. 2b (operation 2 in FIG. 1). Figure 2b after pulling out the control rods around the core.
By forming the control rod pattern, the thermal output of the reactor increases from operating point 1 in FIG. 1 to operating point 2 in FIG. 1 along the solid line. FIG. 3 shows the change in linear power density when the control rods around the core are pulled out from the control rod pattern shown in FIG. 2a. curve 5
shows the change in linear power density in the fuel assembly adjacent to a control rod that is fully inserted in the core periphery when the control rod is moved from fully inserted to fully withdrawn. . Curve 4 shows the linear power density in the fuel assembly that has the maximum linear power density in the center of the core when all the control rods (24 control rods in this example) inserted in the periphery of the core are pulled out. It shows change. Control rods around the core are withdrawn in sequence in 1/24 increments so that they are symmetrical with respect to the center of the core. The black circles in Curve 4 indicate the linear power density of the fuel assembly in the center of the core when all the control rods inserted in the periphery of the core are pulled out to the control rod insertion amount corresponding to the black circles. For example, the second black circle from the left in Figure 3 shows the linear output of the aforementioned fuel assembly when all 24 control rods inserted around the core are pulled out to the 20/24 position. It is density. The linear power density of the fuel assembly adjacent to the control rods that are pulled out from the core periphery is small, even when all the control rods are pulled out, because the leakage of neutrons in the core periphery is large as described above.
It is less than 8KW/ft (Curve 5 in Figure 3). Therefore, even in fuel assemblies located in the periphery of the reactor core and adjacent to the withdrawn control rods, where the change in linear power density is greatest when the control rods are withdrawn, no damage to the fuel rods occurs. However, by pulling out the control rods in the core periphery from the control rod pattern in Figure 2a, the fuel assembly existing in the center of the reactor core has a linear power density of 8KW/8KW as shown in curve 4 in Figure 3. Something that exceeds ft occurs. This is the total amount of change in linear power density until all control rods inserted around the core are fully withdrawn. As mentioned above, the control rods inserted in the periphery of the reactor core are pulled out one by one in order of 1/24 so that they are point symmetrical with respect to the center of the reactor core.
As shown in Figure 6 of the publication, the influence of control rod withdrawal does not affect the fuel assemblies located far from the control rods, so the linear power density of the fuel assemblies located in the center of the reactor core is It does not increase significantly due to withdrawal operations of control rods around the core. In other words, the linear power density of the fuel assembly placed in the center of the core remains the same even if the control rods around the core are pulled out.
The increase rate is about 0.06KW/ft/h. Therefore, even if the control rods around the core are pulled out, the fuel assembly at the center of the core will not be damaged. In addition,
In the vicinity of the reactor core, after a predetermined amount of one control rod has been withdrawn, the next control rod is withdrawn after a predetermined period of time has elapsed in order to accumulate xenon.
このように本実施例では、燃料棒破損をおこさ
ないための前述の第1の事実を考慮した運転制限
を守つて定格出力制御棒パタンを実現したことに
なる。以後、運転点2以降、第2図bの制御棒パ
タンを保持して変化率0.06KW/ft/hを保ちつ
つ炉心流量を増加させれば、100%(定格)出力
を実現できる(第1図の運転点3)の例の全所要
時間は約7日であり従来技術で示した例の1/3に
短縮されている。 In this way, in this example, the rated output control rod pattern was achieved while observing the operational restrictions that took into account the first fact described above to prevent fuel rod damage. After that, from operating point 2 onwards, if the control rod pattern shown in Figure 2b is maintained and the core flow rate is increased while maintaining the rate of change of 0.06 KW/ft/h, 100% (rated) output can be achieved (1st The total time required for the example of operation point 3) in the figure is about 7 days, which is reduced to one third of the example shown in the prior art.
なお、炉心流量をその定格値の50%を越える状
態で第2図aに示す制御棒パタンから炉心周辺部
の制御棒を引抜いた場合には、引抜き制御棒に隣
接する燃料集合体の線出力密度がしきい値を越え
てしまう。従つて、第2図aの制御棒パタンで炉
心周辺部の制御棒を引抜く場合は炉心流量をその
定格値の50%以下にする必要がある。 Note that if the control rods around the core are pulled out from the control rod pattern shown in Figure 2a with the core flow rate exceeding 50% of its rated value, the linear output of the fuel assembly adjacent to the pulled control rods will be reduced. The density exceeds the threshold. Therefore, when withdrawing the control rods around the core using the control rod pattern shown in Figure 2a, it is necessary to reduce the core flow rate to 50% or less of its rated value.
定格制御棒パタンが第2図に示した制御棒パタ
ンと異なる場合を第4図に示す。第4図bに示し
た制御棒パタンが定格出力を実現する目標制御棒
パタンであり、第4図aに示した制御棒パタン
が、目標制御棒パタンにさらに炉心周辺部に複数
本の制御棒を挿入したパタンである。このときの
運転操作方法は、第1の実施例で示した方法と同
じであり、この方法により前記事実1を考慮した
運転制限を守つて100%(定格)出力を実現でき
る。 FIG. 4 shows a case where the rated control rod pattern is different from the control rod pattern shown in FIG. 2. The control rod pattern shown in Figure 4b is the target control rod pattern that realizes the rated output, and the control rod pattern shown in Figure 4a is the target control rod pattern with multiple control rods around the core. This is a pattern with . The operating method at this time is the same as that shown in the first embodiment, and by this method, 100% (rated) output can be achieved while observing the operating restrictions that take Fact 1 above into consideration.
炉心周辺部に挿入する制御棒本数、その挿入深
さはしきい値が8KW/ft以下となるように出力
レベルを下げるのに十分であるように決めればよ
い。その目安は出力密度51KW/l、電気出力
784MWのBWRで全挿入制御棒20本である。こ
の挿入制御棒の本数は定格出力を出す制御棒パタ
ンの最大線出力密度に比例すると考えてよい。 The number of control rods to be inserted into the periphery of the reactor core and the depth of their insertion may be determined to be sufficient to reduce the power level so that the threshold value is 8 KW/ft or less. The standard is power density 51KW/l, electrical output
It is a 784MW BWR with a total of 20 inserted control rods. The number of inserted control rods can be considered to be proportional to the maximum linear power density of the control rod pattern that produces the rated output.
さらに前述した各実施例は、制御棒のパタン交
換などにも適用できる。つまり制御棒パタン交換
の目標パタンに周辺制御棒を挿入した状態を炉心
流量を低下させ(定格炉心流量の〜40%)たのち
実現し、その後周辺部制御棒を引抜くという実施
例1で示した運転操作法を行えばよい。 Furthermore, each of the embodiments described above can be applied to pattern exchange of control rods, etc. In other words, as shown in Example 1, a state in which the peripheral control rods are inserted into the target pattern for control rod pattern exchange is achieved after reducing the core flow rate (~40% of the rated core flow rate), and then the peripheral control rods are pulled out. All you have to do is use the following driving techniques.
なお明細書中で炉心周辺部制御棒とは、炉心最
外周の制御棒およびそれに隣接する制御棒をい
う。 In this specification, the core peripheral control rods refer to the outermost control rods of the core and the control rods adjacent thereto.
以上説明したごとく本発明になる運転方法を用
いれば、燃料の健全性を損うことがなく短時間に
目標出力運転状態を実現でき、稼動率向上の効果
は大きく産業上の効果は大なるものである。 As explained above, if the operating method of the present invention is used, the target output operating state can be achieved in a short time without impairing the integrity of the fuel, and the effect of improving the operating rate is large and the industrial effect is great. It is.
第1図および第2図は、本発明の一実施例の説
明図、第3図は、第2図の制御棒パタンaから、
第2図の制御棒パタンb(目標制御棒パタン)ま
で周辺制御棒を引抜くときの操作制御棒隣接燃料
の最大線出力密度と炉心中央部での最大線出力密
度の変化を示す図、第4図は、本発明の他の実施
例を示す図である。
1……目標制御棒パタンにさらに周辺制御棒を
挿入した制御棒パタンを実現したときの運転点、
2……目標制御棒パタンを実現したときの運転
点、3……定格出力運転点、4……炉心中央部で
の最大線出力密度、5……操作制御棒に隣接した
燃料集合体での最大線出力密度。
1 and 2 are explanatory diagrams of an embodiment of the present invention, and FIG. 3 is a control rod pattern a of FIG.
A diagram showing the change in the maximum linear power density of the fuel adjacent to the operating control rods and the maximum linear power density at the center of the core when the peripheral control rods are pulled out to control rod pattern b (target control rod pattern) in Fig. 2. FIG. 4 is a diagram showing another embodiment of the present invention. 1... Operating point when realizing a control rod pattern in which peripheral control rods are further inserted into the target control rod pattern,
2... Operating point when the target control rod pattern is achieved, 3... Rated power operating point, 4... Maximum linear power density at the center of the core, 5... At the fuel assembly adjacent to the operating control rod. Maximum linear power density.
Claims (1)
も前記炉心中央部を取り囲む炉心周辺部で制御棒
が全部引抜かれてなる目標制御棒パターンに、前
記炉心周辺部で1本または複数本の制御棒を更に
挿入した状態を付加した制御棒パターンでの運転
を、炉心流量定格値の50%以下の炉心流量範囲で
のみ行い、その後、前記炉心流量定格値の50%以
下の炉心流量範囲で、前記炉心周辺部に挿入され
た前記制御棒を引抜いて前記目標制御棒パターン
を形成し、その状態で出力上昇率の所定の制限値
を守るように炉心流量を増加させて最終目標であ
る設定レベルまで原子炉出力を上昇させる沸騰水
型原子炉の運転方法。1 A target control rod pattern in which a predetermined amount of control rods are inserted in the central part of the reactor core, and all control rods are withdrawn in the peripheral part of the core surrounding the central part of the reactor, one or more control rods are inserted in the peripheral part of the reactor core. Operation with a control rod pattern with additional rods inserted is performed only in a core flow rate range of 50% or less of the core flow rate rated value, and then in a core flow rate range of 50% or less of the core flow rate rated value, The control rods inserted into the peripheral area of the reactor core are pulled out to form the target control rod pattern, and in this state, the core flow rate is increased so as to maintain a predetermined limit value for the rate of increase in power, thereby achieving the final target set level. A method of operating a boiling water reactor that increases reactor output to .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2658080A JPS56124087A (en) | 1980-03-05 | 1980-03-05 | Operating method of bwr type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2658080A JPS56124087A (en) | 1980-03-05 | 1980-03-05 | Operating method of bwr type reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56124087A JPS56124087A (en) | 1981-09-29 |
| JPH024875B2 true JPH024875B2 (en) | 1990-01-30 |
Family
ID=12197485
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2658080A Granted JPS56124087A (en) | 1980-03-05 | 1980-03-05 | Operating method of bwr type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS56124087A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60104295A (en) * | 1983-11-11 | 1985-06-08 | 株式会社日立製作所 | How to start a boiling water reactor |
| JPS60224093A (en) * | 1984-04-20 | 1985-11-08 | 株式会社東芝 | Method of operating boiling water type reactor |
| US5418040A (en) * | 1991-08-05 | 1995-05-23 | Honda Giken Kogyo Kabushiki Kaisha | Automobile fuel tank with damper layer and method of manufacturing such damper layer |
-
1980
- 1980-03-05 JP JP2658080A patent/JPS56124087A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56124087A (en) | 1981-09-29 |
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