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JPH0527075B2 - - Google Patents

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Publication number
JPH0527075B2
JPH0527075B2 JP58181516A JP18151683A JPH0527075B2 JP H0527075 B2 JPH0527075 B2 JP H0527075B2 JP 58181516 A JP58181516 A JP 58181516A JP 18151683 A JP18151683 A JP 18151683A JP H0527075 B2 JPH0527075 B2 JP H0527075B2
Authority
JP
Japan
Prior art keywords
core
fuel
loaded
enrichment
fuel assemblies
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
JP58181516A
Other languages
Japanese (ja)
Other versions
JPS6071987A (en
Inventor
Ritsuo Yoshioka
Shoichi Watanabe
Hiromi Ishida
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP58181516A priority Critical patent/JPS6071987A/en
Publication of JPS6071987A publication Critical patent/JPS6071987A/en
Publication of JPH0527075B2 publication Critical patent/JPH0527075B2/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

  • Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
  • Fuel Cell (AREA)

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は燃料集合体の装荷方法を改善すること
によつて燃料の経済性向上を図つた沸騰水系原子
炉の運転方法に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a method of operating a boiling water nuclear reactor that improves fuel economy by improving the method of loading fuel assemblies.

[発明の技術的背景] 一般に沸騰水形原子炉は第1図に示す如く断面
十字形の制御棒1……の周囲に4体の燃料集合体
2……を装荷して単位格子3……を構成し、さら
に第2図に示す如くこれら単位格子3……を複数
個格子状態に配列して炉心を構成している。とこ
ろで、このような沸騰水形原子炉は約1年すなわ
ち1サイクル運転毎に燃料集合体の交換がおこな
われるが、この燃料集合体は1〜4サイクルの間
燃焼されるように設計されており、燃料交換の際
には全燃料集合体のうちの1/3〜1/4ずつが交換さ
れる。したがつて、燃料集合体を1/3ずつ交換し
て運転した場合、3サイクル以後は燃焼が際も進
んだ燃料集合体、燃焼が中程度進んだ燃料集合
体、燃焼が進んでいない燃料集合体、すなわち無
限増倍係数が最低、中程度、最高、の燃料集合体
が1/3ずつ装荷された炉心となり、以降は燃料交
換毎に無限増倍係数最低の燃料集合体を取出し、
代わりに新燃料集合体を装荷すれば以降同じ状態
の炉心が維持され、このような炉心を平衡炉心と
称している。しかし、原子炉を建設して初めて燃
料集合体を装荷した炉心すなわち初装荷炉心にお
いては全燃料集合体が新燃料集合体であるので、
初めの2〜3サイクルの間は完全に燃焼されてい
ない燃料集合体が燃料交換の際に炉心から取出さ
れることになり、不経済であつた。
[Technical Background of the Invention] In general, a boiling water nuclear reactor, as shown in Fig. 1, has four fuel assemblies 2 loaded around a control rod 1 having a cross-shaped cross section, and a unit grid 3. Further, as shown in FIG. 2, a plurality of these unit lattices 3... are arranged in a lattice form to constitute the reactor core. Incidentally, in such boiling water reactors, the fuel assembly is replaced approximately every year, or every cycle of operation, but this fuel assembly is designed to be burned for 1 to 4 cycles. When replacing fuel, 1/3 to 1/4 of the total fuel assembly is replaced. Therefore, when operating by replacing fuel assemblies by 1/3, after the 3rd cycle, there will be fuel assemblies with very advanced combustion, fuel assemblies with moderate combustion, and fuel assemblies with no progress in combustion. In other words, the core is loaded with 1/3 of the fuel assemblies with the lowest, middle, and highest infinite multiplication coefficients, and after each fuel change, the fuel assembly with the lowest infinite multiplication coefficient is taken out.
If a new fuel assembly is loaded instead, the core will remain in the same state from then on, and such a core is called an equilibrium core. However, in the reactor core loaded with fuel assemblies for the first time after constructing the reactor, that is, in the first loaded reactor core, all fuel assemblies are new fuel assemblies, so
During the first two to three cycles, fuel assemblies that have not been completely burned must be removed from the core during fuel exchange, which is uneconomical.

このような不具合を改善するため、初装荷炉心
において燃料集合体をたとえば高濃縮度、低濃縮
度、低濃縮度の3種類の濃縮度のものすなわち無
限増倍係数が最高、中程度、最低、の3種類のも
のを用意し、これら3種類の燃料集合体を1/3ず
つ装荷して初装荷炉心を構成することがなされて
いる。このような初装荷炉心は前記平衡炉心と同
じ状態であるため、第1回の燃料交換の時から無
限増倍係数が低い燃料集合体すなわち燃料が十分
に進んだと同じ状態の燃料集合体が炉心から取出
されるため、燃料の経済性が向上する。
In order to improve this problem, the fuel assemblies in the initial loading core have three types of enrichment: high enrichment, low enrichment, and low enrichment. Three types of fuel assemblies are prepared, and 1/3 of each of these three types of fuel assemblies is loaded to form the initial loading core. Since such an initially loaded core is in the same state as the equilibrium core, a fuel assembly with a low infinite multiplication coefficient from the time of the first fuel exchange, that is, a fuel assembly in the same state as when the fuel has sufficiently advanced, is Since it is removed from the core, fuel economy is improved.

[背景技術の問題点] ところで、商業用の原子炉では燃料の経済性を
より向上することが要望されているが、上述の如
き方法では燃料の経済性をこれ以上向上させるこ
とは困難であつた。すなわち、上述の方法は初装
荷炉心を平衡炉心と同じ状態とするものであるか
ら、燃料交換の際に炉心から取出される燃料集合
体の体数および新たに装荷する新燃料集合体の体
数はいずれも全燃料集合体の1/3ずつに固定され、
これらを変更する余地はない。また、沸騰水形原
子炉では原子炉運転中には一部の制御棒のみが調
整棒として炉心処内に挿入され、残りの制御棒は
全引抜き状態にあり、この調整棒によつて炉心の
反応度の調整がなされる。これによつて、この調
整棒を含む単位格子すなわちコントロールセルは
運転中に出力の変動を伴い、このコントロールセ
ル内に装荷されている燃料集合体は熱的条件が厳
しい。このため、このコントロールセル内には出
力の低い燃料集合体すなわち無限増倍係数が最低
の燃料集合体を装荷し、全燃料集合体の熱的条件
を平均化し、炉心全体の出力を上げて燃料の効率
的に燃焼を図る必要がある。また、炉心の最外周
部では炉心外に漏れる中性子の量が多いので、こ
の最外周部にも無限増倍係数が最低の燃料集合体
を装荷し、中性子の漏れ量を少なくする必要があ
る。したがつて、このような条件から燃料集合体
の装荷パターンを変更する余地も水ない。よつ
て、燃料交換の際の燃料集合体の交換体数や燃料
集合体の装荷パターンの変更が自由にできないた
め、燃料の経済性を向上させる余地がほとんどな
いものである。
[Problems with the Background Art] Incidentally, there is a demand for further improvement in fuel economy in commercial nuclear reactors, but it is difficult to further improve fuel economy with the methods described above. Ta. In other words, since the method described above puts the initially loaded reactor core in the same state as the equilibrium core, the number of fuel assemblies to be removed from the reactor core during refueling and the number of new fuel assemblies to be newly loaded are are fixed to 1/3 of the total fuel assembly,
There is no room to change these. In addition, in a boiling water reactor, only some control rods are inserted into the reactor core as adjustment rods during reactor operation, and the remaining control rods are completely withdrawn. Adjustment of reactivity is made. As a result, the unit grid, ie, the control cell that includes this adjustment rod, undergoes fluctuations in output during operation, and the fuel assembly loaded in this control cell is subject to severe thermal conditions. For this reason, a fuel assembly with low output, that is, a fuel assembly with the lowest infinite multiplication factor, is loaded in this control cell, and the thermal conditions of all fuel assemblies are averaged to increase the output of the entire core and fuel It is necessary to aim for efficient combustion. Furthermore, since a large amount of neutrons leak out of the core at the outermost periphery of the core, it is necessary to load fuel assemblies with the lowest infinite multiplication coefficients also in this outermost periphery to reduce the amount of neutrons leaking. Therefore, there is no room for changing the loading pattern of the fuel assembly under these conditions. Therefore, since it is not possible to freely change the number of fuel assemblies to be replaced or the loading pattern of fuel assemblies during fuel exchange, there is little room for improving fuel economy.

〔発明の目的〕[Purpose of the invention]

本発明は以上の事情に基づいてなされたもの
で、その目的とするところは燃料の経済性をより
向上させることができる沸騰水形原子炉の運転方
法を提供することにある。
The present invention has been made based on the above circumstances, and its purpose is to provide a method of operating a boiling water reactor that can further improve fuel economy.

〔発明の概要〕[Summary of the invention]

すなわち本発明は、初装荷炉心においては上記
燃料集合体を濃縮度の互いに異なる複数種類と
し、最高濃縮度の燃料集合体を炉心の最外周の位
置に装荷し、また最低濃縮度の燃料集合体を調整
棒として使用する制御棒を含む単位格子に装荷
し、1サイクル運転した後には無限増倍係数の最
も低い燃料集合体を炉心の最外周の位置および調
整棒として使用する制御棒を含む単位格子に装荷
するものである。したがつて、初装荷炉心におい
ては中性子の漏れによつて出力が低くなる炉心の
最外周部に無限増倍係数の高い最高濃縮度の燃料
集合体が装荷されるので、第1サイクルの燃焼で
は炉心全体の出力が増大し、燃料集合体が効率的
に燃焼させることができる。また、この初装荷炉
心では最外周に最高濃縮度の燃料集合体が装荷さ
れるので、この分だけ最低濃縮度の燃料集合体の
装荷体数が少なくある。したがつて、第1回の燃
料交換では最低濃縮度の燃料集合体が十分に燃料
の進んだ状態で炉心から取出され、しかもこの最
低濃縮度の燃料集合体の体数は少ないのでこの第
1サイクルにおける燃料の経済性は大幅に向上す
る。なお、初装荷炉心における最高濃縮度の燃料
集合体の装荷体数は従来より増加するが、これら
最高濃縮度の燃料集合体はいずれ平衡炉心に移行
する間に燃焼が進んだ状態で炉心から取出される
ので、数サイクルにわたる期間でみればこの最高
濃縮度の燃料集合体の装荷体数の増加は燃料の経
済性の低下を招くことはないものである。
That is, in the present invention, in the initially loaded reactor core, a plurality of types of fuel assemblies with different enrichments are used, and the fuel assemblies with the highest enrichment are loaded at the outermost position of the core, and the fuel assemblies with the lowest enrichment are loaded at the outermost position of the core. is loaded into a unit grid containing control rods used as adjustment rods, and after one cycle of operation, the fuel assembly with the lowest infinite multiplication factor is placed at the outermost periphery of the core and the unit containing control rods used as adjustment rods. It is loaded onto a grid. Therefore, in the first-loaded core, the highest enrichment fuel assembly with a high infinite multiplication factor is loaded at the outermost periphery of the core, where output decreases due to neutron leakage. The overall power of the core increases, and the fuel assemblies can burn more efficiently. Furthermore, in this initially loaded core, the fuel assemblies with the highest enrichment are loaded on the outermost periphery, so the number of fuel assemblies with the lowest enrichment is reduced accordingly. Therefore, in the first refueling, the fuel assemblies with the lowest enrichment are taken out from the core with sufficient fuel, and since the number of fuel assemblies with the lowest enrichment is small, this first Fuel economy in the cycle is significantly improved. Note that although the number of fuel assemblies with the highest enrichment in the initially loaded core will increase compared to before, these fuel assemblies with the highest enrichment will eventually be removed from the reactor in a state where combustion has progressed during the transition to the equilibrium core. Therefore, over a period of several cycles, this increase in the number of fuel assemblies with the highest enrichment degree does not result in a decrease in fuel economy.

〔発明の実施例〕[Embodiments of the invention]

以下第3図ないし第6図を参照して本発明の一
実施例を説明する。第3図は初装荷炉心の燃焼集
合体の装荷パターンを示す。この第3図ないし第
6図は1/4炉心を模式的に示すもので、A……は
制御棒、まず目B……は燃料集合体、C′……は調
整棒として使用される制御棒を含む単位格子すな
わちコントロールセルを示す。また、燃料集合体
を示すます目B……内に記れた数字は燃料集合体
の種類を示し、これら燃料集合体の装荷パターン
は炉心全体については中心線X−X、Y−Yに対
して全て対称である。そして、この第3図では数
字1は最高濃縮度たとえば濃縮度3.00重量%の燃
料集合体、数字2は中濃縮度たとえば濃縮度2.07
重量%の燃料集合体、数学3は最低濃縮度たとえ
ば濃縮度1.99重量%の燃料集合体を示す。そし
て、この初装荷炉心では最高濃縮度の燃料集合体
B……を炉心の最外周部に装荷し、また最低濃縮
度の燃料集合体をコントロールセルC′に装荷す
る。また、この他の領域には最高濃縮度、中濃縮
度、最低濃縮度の燃料集合体B……をそれぞれ平
均的に分散するように装荷する。したがつて、こ
の炉心な装荷される全燃料集合体の体数は5600体
であり、この1/3は約187体であるが、最高濃縮度
の燃料集合体B……はこれより最外周部に装荷し
た分だけ多い252体であり、また最低濃縮度の燃
料集合体B……はこの分だけ少ない116体、中濃
縮度の燃料集合体B……は約1/3に相当する192体
である。
An embodiment of the present invention will be described below with reference to FIGS. 3 to 6. Figure 3 shows the loading pattern of the combustion assembly in the initially loaded core. These Figures 3 to 6 schematically show the 1/4 core, where A... is the control rod, B... is the fuel assembly, and C'... is the control rod used as the adjustment rod. A unit cell or control cell containing bars is shown. In addition, the numbers written inside square B, which indicates fuel assemblies, indicate the type of fuel assemblies, and the loading pattern of these fuel assemblies is relative to the center lines X-X and Y-Y for the entire core. All are symmetrical. In this Figure 3, number 1 is a fuel assembly with a maximum enrichment, for example, 3.00% by weight, and number 2 is a fuel assembly with a medium enrichment, for example, 2.07% enrichment.
Weight % fuel assembly, Math 3 indicates a fuel assembly with the lowest enrichment, for example 1.99 weight %. In this initial loading core, the fuel assemblies B with the highest enrichment are loaded onto the outermost periphery of the core, and the fuel assemblies with the lowest enrichment are loaded into the control cell C'. Further, fuel assemblies B having the highest enrichment, middle enrichment, lowest enrichment, etc. are loaded in other regions so as to be evenly distributed. Therefore, the total number of fuel assemblies loaded into the core is 5,600, and 1/3 of this is approximately 187, but fuel assembly B with the highest enrichment... The number of fuel assemblies is 252, which is more than the amount loaded in the fuel assembly B, and the fuel assembly B with the lowest enrichment is 116, and the fuel assembly B with the middle enrichment is 192, which is equivalent to about 1/3. It is the body.

そして、このような初装荷炉心のパターンで約
1年すなわち1サイクルの間燃焼させる。このサ
イクルでの燃焼は最高濃縮度の燃料集合体の体数
が多く、しかもこれら最高濃縮度の燃料集合体は
炉心の周辺部に装荷されているので、炉心全体の
出力がより高くかつ平均化され、効率化な燃焼が
なされる。したがつて、最低濃縮度の燃料集合体
B……も効率的に燃焼される。なお、炉心の最外
周装荷された最高濃縮度の燃料集合体B……は中
性子の炉心外への漏れによつて他の領域に装荷さ
れた最高濃縮度の燃料集合体B……よりは燃焼が
進まない。
Then, the core is burned in this initial loading core pattern for about one year, or one cycle. Combustion in this cycle involves a large number of fuel assemblies with the highest enrichment, and since these fuel assemblies with the highest enrichment are loaded around the core, the output of the entire core is higher and more averaged. This results in more efficient combustion. Therefore, the fuel assembly B having the lowest enrichment level is also efficiently combusted. Note that fuel assembly B with the highest enrichment loaded in the outermost area of the core is more likely to burn than fuel assembly B with the highest enrichment loaded in another area due to neutron leakage outside the core. is not progressing.

そして、第1サイクルの運転が終了したら、第
1回の燃料交換をおこなう。この燃料交換では最
低濃縮度であつた燃料集合体B……116体を全
て炉心より取出し、替わりに新燃料集合体116
体を装荷する。そして、この場合の燃料集合体の
装荷パターンを第4図に示す。この第4図中に記
された数字は燃料集合体B……の無限増倍係数の
程度を示し、数字1は無限増倍係数が最高のもの
すなわち新燃料集合体を示し、数字2は無限増倍
係数が中程度のものすなわち初装荷炉心で最高濃
縮度であつたもの、数字3は無限増倍係数が最低
のものすなわち初装荷炉心で中濃縮度であつたも
のである。そして、この第2サイクルでの燃料集
合体の装荷パターンは第4図に示す如く無限増倍
係数が最低のものを炉心の最外周およびコントロ
ールセルC′……に装荷し、この他に領域には無限
増倍係数が最高、中程度、最低のものをそれぞれ
平均に分散して装荷する。
After the first cycle of operation is completed, the first fuel exchange is performed. In this fuel exchange, all 116 fuel assemblies B, which had the lowest enrichment level, were removed from the core, and new fuel assemblies 116 were replaced in their place.
Load the body. The loading pattern of the fuel assembly in this case is shown in FIG. The numbers written in Fig. 4 indicate the degree of infinite multiplication coefficient of fuel assembly B..., number 1 indicates the one with the highest infinite multiplication coefficient, that is, the new fuel assembly, and number 2 indicates the infinite multiplication coefficient. The number 3 indicates a medium multiplication factor, that is, the highest enrichment in the initially loaded core, and the number 3 indicates the lowest infinite multiplication factor, that is, the medium enrichment in the initially loaded core. The loading pattern of the fuel assemblies in this second cycle is as shown in Figure 4, in which the fuel assemblies with the lowest infinite multiplication coefficients are loaded into the outermost periphery of the core and the control cell C'... is loaded by distributing the highest, middle, and lowest infinite multiplication factors into the average.

そして、この装荷パターンで第2サイクルの運
転をおこなう。この第2サイクル以降での装荷パ
ターンは基本的には平衡炉心と同じものであり、
特に燃料の経済性向上を達成するものではなく、
平衡炉心に円滑に移行するためのものである。
Then, a second cycle operation is performed with this loading pattern. The loading pattern after this second cycle is basically the same as the equilibrium core,
It does not particularly improve fuel economy;
This is to ensure a smooth transition to an equilibrium core.

次にこの第2サイクルの運転が終了したら2回
目の燃料交換をおこなう。この燃料交換では初装
荷炉心で中濃縮度の燃料集合体B……192体のう
ちの180体を炉心から取出して残り12体を残し、
替わりに新燃料集合体180を装荷する。したが
つて、この燃料交換では燃料集合体の種類は無限
増倍係数の異なる4種類となり、その装荷パター
ンを第5図示す。この第5図中の数字の1は無限
増倍係数の最も高いものすなわち新燃料集合体を
示し、また数字4は無限増倍係数が最も低いもの
すなわち前述した12体のものである。そして、こ
の第3サイクルの装荷パターンも炉心の最外周お
よびコントロールセルC′………に無限増倍係数の
低い燃料集合体B……を装荷したものである。
Next, when this second cycle operation is completed, a second fuel exchange is performed. In this refueling, 180 out of 192 fuel assemblies B with intermediate enrichment in the initially loaded core were removed from the core, leaving the remaining 12.
Instead, a new fuel assembly 180 is loaded. Therefore, in this fuel exchange, there are four types of fuel assemblies with different infinite multiplication coefficients, and their loading patterns are shown in FIG. The number 1 in FIG. 5 indicates the one with the highest infinite multiplication coefficient, that is, the new fuel assembly, and the number 4 indicates the one with the lowest infinite multiplication coefficient, that is, the 12 units mentioned above. The loading pattern of this third cycle is also such that fuel assemblies B having a low infinite multiplication coefficient are loaded on the outermost periphery of the core and on the control cells C'.

そして、この第3サイクルの運転が終了したら
第3回の燃料交換をおこなう。この第3回の燃料
交換では初装荷炉心で最高濃縮度であつた燃料集
合体B……252体が無限増倍係数が低くなつてい
る。そして、この燃料交換ではこの252体のうち
の152体および第3サイクルで無限増倍係数が最
も低かつた燃料集合体12体を炉心から取出し、替
わりに新燃料集合体164体を装荷する。なお、初
装荷炉心で最高濃縮度であつた燃料集合体B……
のうち炉心に残す100体は初装荷炉心で炉心の最
外周に装荷されていたもの、すなわちあまり燃焼
の進んでいないものを選ぶ。そして、以下このよ
うにして最終的に平衡炉心に移行する。
Then, when the third cycle of operation is completed, a third fuel exchange is performed. In this third refueling, fuel assembly B...252, which had the highest enrichment in the initially loaded core, had a lower infinite multiplication factor. In this fuel exchange, 152 of these 252 fuel assemblies and the 12 fuel assemblies with the lowest infinite multiplication coefficient in the third cycle are removed from the core, and 164 new fuel assemblies are loaded in their place. In addition, fuel assembly B, which had the highest enrichment level in the initially loaded core...
The 100 bodies to be left in the reactor core will be those that were loaded at the outermost periphery of the core during the initial loading, meaning those that have not yet undergone much combustion. Then, in this way, the core finally shifts to an equilibrium core.

〔発明の効果〕〔Effect of the invention〕

上述の如く本発明は、初装荷炉心においては上
記燃焼集合体を濃縮度の互いに異なる複数種類と
し、最高濃縮度の燃料集合体を炉心の最外周の位
置に装荷し、また最低濃縮度の燃料集合体を調整
棒として使用する制御棒を含む単位格子に装荷
し、1サイクル運転した後には無限増倍係数の最
も低い燃料集合体を炉心の最外周の位置および調
整棒として使用する制御棒を含む単位格子に装荷
するものである。したがつて、初装荷炉心におい
ては中性子の漏れによつて出力が低くなる炉心の
最外周部に無限増倍係数の高い最高濃縮度の燃料
集合体が装荷されるので、第1サイクルの燃焼で
は炉心全体の出力が増大し、燃料集合体を効率的
に燃焼させることができる。また、この初装荷炉
心では最外周に最高濃縮度の燃料集合体が装似さ
れるので、この分だけ最低濃縮度の燃料集合体の
装荷体数が少なくなる。したがつて、第1回の燃
料交換では最低濃縮度の燃料集合体が十分に燃焼
の進んだ状態で炉心から取出され、しかもこの最
低濃縮度の燃焼集合体の体数は少ないのでこの第
1サイクルにおける燃料の経済性は大幅に向上す
る。また、初装荷炉心における最高濃縮度の燃料
集合体の装荷体数は従来より増加するが、これら
最高濃縮度の燃料集合体はいずれ平衡炉心の移行
する間に燃焼が進んだ状態で炉心から取出される
ので、数サイクルにわたる期間でみればこの最高
濃縮度の燃料集合体の装荷体数の増加は燃料の経
済性の低下を招くことはない等その効果は大であ
る。
As described above, the present invention provides a plurality of types of combustion assemblies with different enrichments in the initially loaded reactor core, and loads the fuel assemblies with the highest enrichment at the outermost position of the core, and loads the fuel assemblies with the highest enrichment at the outermost position of the core. The fuel assembly is loaded into a unit cell containing control rods used as adjustment rods, and after one cycle of operation, the fuel assembly with the lowest infinite multiplication factor is placed at the outermost periphery of the core and the control rods used as adjustment rods are loaded. This is to load the unit cell containing the Therefore, in the first-loaded core, the highest enrichment fuel assembly with a high infinite multiplication factor is loaded at the outermost periphery of the core, where output decreases due to neutron leakage. The output of the entire reactor core increases, and the fuel assemblies can be burned efficiently. In addition, in this initially loaded core, the fuel assemblies with the highest enrichment are placed on the outermost periphery, so the number of fuel assemblies with the lowest enrichment is reduced accordingly. Therefore, in the first refueling, the fuel assembly with the lowest enrichment is taken out from the core in a state where combustion has progressed sufficiently, and since the number of combustion assemblies with the lowest enrichment is small, this first Fuel economy in the cycle is significantly improved. In addition, although the number of fuel assemblies with the highest enrichment in the initially loaded core will increase compared to before, these fuel assemblies with the highest enrichment will eventually be removed from the core in a state where combustion has progressed during the transition to an equilibrium core. Therefore, over a period of several cycles, an increase in the number of loaded fuel assemblies with the highest enrichment degree has a great effect, such as not causing a decrease in fuel economy.

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

第1図は単位格子の模式的な平面図、第2図は
炉心の一部の模式的な平面図である。第3図ない
し第6図は本発明の一実施例を説明する燃料集合
体の装荷パターンを示す模式的な図である。 A……制御棒、B……燃料集合体、C……単位
格子、C′……コントロールセル。
FIG. 1 is a schematic plan view of a unit cell, and FIG. 2 is a schematic plan view of a part of the core. 3 to 6 are schematic diagrams showing loading patterns of fuel assemblies explaining one embodiment of the present invention. A...Control rod, B...Fuel assembly, C...Unit cell, C'...Control cell.

Claims (1)

【特許請求の範囲】[Claims] 1 制御棒の周囲に4体の燃料集合体を装荷して
単位格子を構成し、この単位格子を複数個格子状
に配列して炉心を構成した沸騰水形原子炉を運転
する方法において、初装荷炉心においては上記燃
料集合体を濃縮度の互いに異なる複数種類とし、
最高濃縮度の燃料集合体を炉心の最外周の位置に
装荷し、また最低濃縮度の燃料集合体を調整棒と
して使用する制御棒を含む単位格子に装荷し、1
サイクル運転した後には無限増倍係数の最も低い
燃料集合体を炉心の最外周の位置および調整棒と
して使用する制御棒を含む単位格子に装荷するこ
とを特徴とする沸騰水形原子炉の運転方法。
1 This is the first method for operating a boiling water reactor in which four fuel assemblies are loaded around a control rod to form a unit cell, and a core is formed by arranging a plurality of unit cells in a lattice pattern. In the loaded core, the fuel assemblies are of multiple types with different enrichment levels,
The fuel assembly with the highest enrichment is loaded at the outermost position of the core, and the fuel assembly with the lowest enrichment is loaded into a unit grid containing control rods used as adjustment rods.
A method for operating a boiling water reactor, characterized in that after cycle operation, the fuel assembly with the lowest infinite multiplication factor is loaded at the outermost periphery of the core and into a unit cell containing control rods used as adjustment rods. .
JP58181516A 1983-09-29 1983-09-29 Method of operating boiling-water reactor Granted JPS6071987A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58181516A JPS6071987A (en) 1983-09-29 1983-09-29 Method of operating boiling-water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58181516A JPS6071987A (en) 1983-09-29 1983-09-29 Method of operating boiling-water reactor

Publications (2)

Publication Number Publication Date
JPS6071987A JPS6071987A (en) 1985-04-23
JPH0527075B2 true JPH0527075B2 (en) 1993-04-20

Family

ID=16102118

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58181516A Granted JPS6071987A (en) 1983-09-29 1983-09-29 Method of operating boiling-water reactor

Country Status (1)

Country Link
JP (1) JPS6071987A (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006234396A (en) * 2005-02-22 2006-09-07 Nuclear Fuel Ind Ltd Reactor fuel operation method
JP2011169858A (en) * 2010-02-22 2011-09-01 Global Nuclear Fuel-Japan Co Ltd Initial loading core of boiling water reactor
JPWO2015059737A1 (en) * 2013-10-21 2017-03-09 株式会社日立製作所 Nuclear reactor core

Also Published As

Publication number Publication date
JPS6071987A (en) 1985-04-23

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