JPS6071987A - Method of operating boiling-water reactor - Google Patents

Method of operating boiling-water reactor

Info

Publication number
JPS6071987A
JPS6071987A JP58181516A JP18151683A JPS6071987A JP S6071987 A JPS6071987 A JP S6071987A JP 58181516 A JP58181516 A JP 58181516A JP 18151683 A JP18151683 A JP 18151683A JP S6071987 A JPS6071987 A JP S6071987A
Authority
JP
Japan
Prior art keywords
core
fuel
fuel assemblies
loaded
enrichment
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.)
Granted
Application number
JP58181516A
Other languages
Japanese (ja)
Other versions
JPH0527075B2 (en
Inventor
律夫 吉岡
庄一 渡辺
ひろみ 石田
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
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group 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 Toshiba Corp, Nippon Genshiryoku Jigyo KK, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
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)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

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って
燃料の経済性向上を図った沸騰水形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173〜1/′4ずっが交換
される。
[Technical Background of the Invention] In general, a boiling water nuclear reactor is constructed by loading four fuel assemblies 2 around a control rod 1 having a cruciform cross section as shown in FIG. . . , and as shown in FIG. 2, a plurality of these unit lattices 3 . . . are arranged in a lattice shape to constitute a 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. , 173 to 1/4 of the total fuel assemblies are replaced during refueling.

したがって、燃料集合体を1/3ずっ交換して運転した
場合、3サイクル以後は燃焼が最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
の炉心か緒持され、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l;炉心すなわち初装荷炉心においては全燃料集合
体か新燃料集合体であるので、初めの2へ・3量1イク
ルの間は完全に燃焼されていない燃料集合体か燃料交換
の際に炉心から取出されることに/jす、不経済であっ
た。
Therefore, when operating with fuel assemblies replaced every third, the fuel assembly with the most advanced combustion after the 3rd cycle,
The core is loaded with 1/3 of fuel assemblies in which combustion has progressed to a moderate degree, fuel assemblies in which combustion has not progressed, that is, fuel assemblies with infinite multiplication coefficients of the lowest, medium, and highest.
Thereafter, every time the fuel is replaced, the fuel assembly with the lowest infinite multiplication factor is taken out and a new fuel assembly is loaded in its place, so that the core remains in the same state from then on, and such a core is called an equilibrium core. However, the fuel assemblies are loaded for the first time after constructing a nuclear reactor; in the reactor core, that is, the first loaded reactor core, it is either all fuel assemblies or new fuel assemblies, so during the first 2 and 3 cycles, the fuel assemblies are completely loaded. This was uneconomical as unburned fuel assemblies had to be removed from the reactor core during refueling.

このような不員合を改善するため、初装荷炉心において
燃料集合体をたとえば高濃縮度、中濃縮度、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17′3す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焼が十分に
進んたど同じ状態の燃料集合体が炉心から取出されるた
め、燃H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, medium enrichment, and low enrichment, i.e., those with the highest infinite multiplication factor, medium enrichment, and At least three types of fuel assemblies are prepared, and three 17'3 fuel assemblies of these three types are loaded to form the initial loading core. Since such an initially loaded core is in the same state as the above-mentioned equilibrium core, fuel assemblies with a low infinite multiplication factor from the time of the first fuel exchange, that is, fuel assemblies in the same state even if combustion has progressed sufficiently, Since it is taken out from the core, the economy of fuel H is improved.

[背明技術の問題点] 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った。り
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111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、この調整棒によって炉心の反応度の調整がなさ
れる。よって、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。
[Problems with the background technology] By the way, 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. there were. 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 limited. The number of bodies is fixed at 1/3 of the total combustion 111 assembly in each case, and 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. Adjustments are made. Therefore, the unit grid, that is, the control cell containing this adjustment rod, is accompanied by fluctuations in output during operation, and the fuel assembly loaded in this control cell is subject to severe thermal conditions.

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な燃焼を図る必要がある。また
、炉心の最外周部では炉心例に漏ね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(■れ樋を少なくする必要がある
。したがって、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少ない。よって、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↑η−を向上さ
1!る余地がほとんどないものである。
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. In addition, since there is a large amount of neutrons leaking at the outermost periphery of the core, it is necessary to load the fuel assembly with the lowest infinite multiplication coefficient also in this outermost periphery to reduce the number of neutron troughs. Therefore, there is little room to change the loading pattern of fuel assemblies due to these conditions.Therefore, it is not possible to freely change the number of fuel assemblies to be replaced during fuel exchange or the loading pattern of fuel assemblies. Therefore, there is almost no room for improving fuel economy ↑η-.

(発明の目的) 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
(Object of the Invention) 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〕 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1■縮度
の燃料集合体を炉心の最外周の位置に装荷(2、また最
低濃縮度の燃料集合体を調整棒として使用するイ制御棒
を含む単位格子に装荷し、15− 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。したがっ
て、初装荷炉心においては中性子の漏れによって出力が
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荷されるので、この分
だ(〕最低濃縮度の燃料集合体の装荷体数が少なくなる
。したがって、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、−〇− 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。
"Summary of the Invention" That is, the present invention provides a method in which, in the initial loading core, the fuel assemblies are of a plurality of types with different enrichment degrees, and the fuel assemblies with a maximum degree of 1cm are loaded at the outermost position of the core. In addition, the fuel assembly with the lowest enrichment is loaded into the unit cell containing the control rods used as adjustment rods, and after 15-cycle operation, the fuel assembly with the lowest infinite multiplication factor is placed at the outermost position of the core. It is loaded into the unit grid that includes the control rods used as adjustment rods.Therefore, in the initially loaded reactor core, the highest enrichment fuel with a high infinite multiplication factor is placed at the outermost periphery of the core, where the output decreases due to neutron leakage. Since the fuel assemblies are loaded, the output of the entire core increases in the first cycle of combustion, and the fuel assemblies can be burned efficiently.In addition, in this initially loaded core, the highest enriched fuel is placed on the outermost periphery. This is because the fuel assemblies with the lowest enrichment are loaded, so the number of loaded fuel assemblies with the lowest enrichment is reduced. Therefore, in the first refueling, the fuel assemblies with the lowest enrichment are not fully burned. It was taken out of the reactor core in a state of
Moreover, since the number of fuel assemblies with the lowest enrichment is small, the fuel economy in this first cycle is greatly 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 -0- several cycles, this increase in the number of fuel assemblies loaded with the highest enrichment does not cause 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料集合体の装荷パタ
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−・・・は調整捧と1ノで使用され
る制御棒を含む単位格子すなわら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・・・内に配れた
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72は中濃縮度たどえば濃縮度2゜07Φ品%
の燃料集合体、数字3は最低濃縮度だとλば濃縮度1.
99重量%の燃料集合体を示す。
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 fuel assemblies in the initial loading core. These Figures 3 to 6 schematically show the '1/4 reactor core, where A... is the control rod, first B...
. indicates a fuel assembly, and C-... indicates a unit grid, ie, a control cell, containing a regulating rod and a control rod used in No. 1. In addition, the numbers placed within squares B... indicating fuel assemblies indicate the type of fuel assemblies, and the loading pattern of these fuel assemblies is based on the center line X-X, Y-Y for the entire core.
All are symmetrical. In this Figure 3, the number 1 is the fuel assembly with the highest enrichment, for example, 3.00% by weight, and the number 72 is the medium enrichment, which means the enrichment is 2°07Φ product.
In the fuel assembly, the number 3 is the lowest enrichment, and if λ is the enrichment 1.
99% by weight fuel assembly is shown.

ぞして、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。したがって、この炉心に装荷される全燃料集合
体の体数は560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たけ多い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。
Therefore, in this initially loaded core, fuel assembly B with the highest enrichment
... is loaded onto the outermost periphery of the core, and the fuel assembly with the lowest enrichment is loaded into the control cell C-. In addition, fuel assemblies B having the highest enrichment, intermediate enrichment, and lowest enrichment are loaded in other regions so as to be evenly distributed. Therefore, the total number of fuel assemblies loaded in this core is 560, and 1/3 of this number is about 187, but fuel assemblies B with the highest enrichment... The number of fuel assemblies loaded is 252, which is the largest number, and the lowest enrichment fuel assembly B... is 116, which is the same number as the number loaded.
There are 192 medium enrichment fuel assemblies B, which corresponds to about 1/'3.

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
率的な燃焼がなされる。したがって、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J、っ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. and efficient combustion. Therefore, even the fuel assembly B with the lowest enrichment level is efficiently combusted. In addition, fuel assemblies B with the highest enrichment loaded in the outermost area of the reactor core are affected by leakage of neutrons to the outside of the core, and fuel assemblies B with the highest enrichment loaded in other areas...・Combustion does not proceed as fast as it does.

そして、第1切イ/フ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!Ii!度で
あ−)だ燃料集合体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
度であったもの、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ったものである。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
他の領域には無限増倍係9− 数が最高、中程度、最低のものをそれぞれ平均に分散1
ノで装荷する。
Then, after the first cut/full operation is completed, the first fuel change is performed. This fuel exchange sucks! Ii! At the same time, all 116 fuel assemblies B... were removed from the reactor core, and 116 new fuel assemblies were loaded in their place. The loading pattern of the fuel assembly in this case is shown in FIG. The numbers written in this Figure 4 are for fuel assembly B...
The number 1 indicates the highest infinite multiplication factor, that is, the new fuel assembly, and the number 2 indicates the one with the intermediate infinite multiplication factor, that is, the highest enrichment in the initial loading core. The number 3 is the one with the lowest infinite multiplication factor, that is, the one with medium enrichment in the initially loaded core. The loading pattern of the fuel assemblies in this second cycle is as shown in Fig. 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'... has an infinite multiplier of 9 - the highest, middle, and lowest numbers have an average variance of 1
Load with no.

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ザ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 the second cycle is basically the same as the balanced core, and is not intended to particularly improve fuel economy, but to smoothly transition to the balanced 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。したがって、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10− 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 fuel exchange, 180 of the 192 medium-enriched fuel assemblies B in the initially loaded core are removed from the core, the remaining 12 are left, and new fuel assemblies 180 are loaded in their place. Therefore, in this fuel exchange, there are four types of fuel assemblies with different infinite multiplication coefficients,
The loading pattern is 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 with a low infinite multiplication coefficient 10 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った燃料集合体B・・・2527
+、が最も無限増倍係数が低くなっている。イして、こ
の燃料交換ではこの252体のうちの752体c15よ
び第3ザイクルで無限増倍係数が最も低か・)だ燃料集
合体12体を炉心から取出し、替わりに新燃料集合体1
64体を装荷すズ)。なお、初装荷炉心で最高濃縮度で
あった燃料集合体B・・・のうら炉心に残す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
わら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...2527, which had the highest enrichment in the initially loaded core,
+ has the lowest infinite multiplication coefficient. Therefore, in this fuel exchange, 12 fuel assemblies with the lowest infinite multiplication coefficient in the third cycle and 752 of these 252 fuel assemblies c15 are removed from the core, and new fuel assemblies 1 are replaced in their place.
(loaded with 64 bodies). The 100 bodies left in the back of fuel assembly B, which had the highest enrichment level in the first loaded core, are those that were loaded at the outermost periphery of the core in the first loaded core, in other words, the fuel assemblies that had not progressed to much combustion. Choose the one that isn't there. Then, in this way, the core finally shifts to an equilibrium core.

(発明の効果) 上述の如く本発明(J、初装荷炉心においては上記燃F
l集合体を濃縮度の互いに異なる複数種類と1)、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(it ai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。したがって、初装荷炉心
おいては中性子の漏れによっ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罷外周に最高ill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なる。したがって、
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。また、初装
荷炉心におCブ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、故サイクルに1〕I:る期間でみ
ればこの最高濃縮度の燃$1集合11: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。
(Effect of the invention) As mentioned above, the present invention (J)
1) The fuel assemblies with the highest enrichment are loaded at the outermost position of the core, and the fuel assemblies with the highest degree of compression are used as adjustment rods. The unit grid containing the control rods is loaded, and after one cycle of operation, the fuel assembly with the lowest infinite multiplication coefficient is loaded at the outermost periphery of the core and the unit grid containing the control rods used as adjustment rods. Therefore, in the first-loaded reactor core, the highest enrichment fuel assembly with a high infinite multiplication factor is loaded at the outermost part of the core where the output decreases due to neutron leakage. The overall output increases and the fuel assemblies can be burned efficiently.Also, in this initially loaded core, the fuel assemblies with the highest degree of illumination are loaded around the outer periphery of the spark, so the minimum enrichment The number of loaded fuel assemblies is reduced. Therefore,
In the first fuel exchange, 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 fuel assemblies with the lowest enrichment is small, the fuel assemblies in this first cycle are Economic efficiency is greatly improved. In addition, although the number of fuel assemblies with the highest enrichment loaded into the initially loaded core will increase compared to before, these fuel assemblies with the highest enrichment will eventually reach a state where combustion has progressed during the transition to an equilibrium core. Since the fuel is taken out from the core at the same time, the increase in the number of fuels loaded with the highest enrichment fuel set 11: during the period 1]I: of the late cycle will not cause a decrease in the economic efficiency of the fuel. The effect is huge.

【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−・・・・・・=lン1〜ロ
ールセル。 出願人代即人 弁理士 鈴江武彦 13−
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-...=ln1~roll cell. Patent attorney on behalf of the applicant Takehiko Suzue 13-

Claims (1)

【特許請求の範囲】[Claims] 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R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。
In a method of 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 these unit cells in a lattice pattern, the initial loading is In the reactor core, multiple 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 low R enrichment are used as adjustment rods. Load the unit grid containing the control rods, and after one cycle of operation, load the fuel assembly with the lowest infinite multiplication coefficient to the outermost position of the core and the unit grid containing the control rods used as adjustment rods. Characteristic operating method of boiling water reactor.
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 true JPS6071987A (en) 1985-04-23
JPH0527075B2 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)

Cited By (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
WO2015059737A1 (en) * 2013-10-21 2015-04-30 株式会社日立製作所 Nuclear reactor core

Cited By (4)

* 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
WO2015059737A1 (en) * 2013-10-21 2015-04-30 株式会社日立製作所 Nuclear reactor core
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
JPH0527075B2 (en) 1993-04-20

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