JPS5915888A - Bwr type reactor core - Google Patents
Bwr type reactor coreInfo
- Publication number
- JPS5915888A JPS5915888A JP57125350A JP12535082A JPS5915888A JP S5915888 A JPS5915888 A JP S5915888A JP 57125350 A JP57125350 A JP 57125350A JP 12535082 A JP12535082 A JP 12535082A JP S5915888 A JPS5915888 A JP S5915888A
- Authority
- JP
- Japan
- Prior art keywords
- core
- fuel assemblies
- loaded
- enrichment
- fuel
- 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.)
- Pending
Links
Classifications
-
- 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
Landscapes
- Organic Low-Molecular-Weight Compounds And Preparation Thereof (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〕 本発明は沸騰水形原子炉の炉心に関する。[Detailed description of the invention] [Technical field of invention] The present invention relates to the core of a boiling water nuclear reactor.
一般に沸騰水形原子炉の炉心は、制御棒の周囲に４体の
燃料集合体を配置して単位格子を構成し、さらにこの単
位格子の複数個を格子状に配列して構成されている。そ
して、上記燃料集合体は初装荷炉心においては全て濃縮
度の醇しい単一種類のものが使用される．そして、燃料
交換の際には全燃料集合体の１／３〜ＩＡの燃料集合体
が炉心から取シ出され、新燃料集合体と交換される。し
たがって、燃料集合体は最長３〜４サイクルの間にわた
って使用できるようにその濃縮度等が設計されている。Generally, the core of a boiling water reactor is constructed by arranging four fuel assemblies around a control rod to form a unit cell, and further arranging a plurality of these unit cells in a lattice shape. All of the fuel assemblies mentioned above are of a single type with rich enrichment in the initial loading core. At the time of fuel exchange, 1/3 to IA of all fuel assemblies are taken out from the core and replaced with new fuel assemblies. Therefore, the enrichment level etc. of the fuel assembly are designed so that it can be used for a maximum of 3 to 4 cycles.
従来のものは最初の３・−４サイクルの間において、１
〜３サイクルしか燃焼されてｂないすなわちまだ濃縮度
の高い燃料集合体が炉心から取シ出されるので、不経済
であった。また、炉心の周辺部からは中性子が炉心外に
漏れるため、周辺部では出力が低く、中央部では出力が
高くなシ、水平方向の出力分布が不均一となる不具合が
あった。また、制御棒は原子炉運転時には、炉心から完
全に引抜かれ、停止時にのみ炉心に挿入される制御棒と
、運転時にも炉心内に挿入され、反応度制御に用いられ
るいわゆる調整棒として使用されるものとがある。そし
て、この調整棒として使用される制御棒を含む単位格子
（以下コントロールセルと称する）は運転中における制
御棒操作によって出力が大きく変動する。よってこのよ
うなコントロールセル内ニある燃料集合体の熱的条件は
厳しいものとなシ、その健全性に悪影響が生じる。The conventional one has 1 during the first 3-4 cycles.
This was uneconomical because the fuel assembly that had been burned for only ~3 cycles, that is, was still highly enriched, was removed from the core. In addition, neutrons leaked from the periphery of the core, resulting in low output at the periphery and high output at the center, resulting in uneven horizontal power distribution. In addition, control rods are divided into two types: control rods that are completely withdrawn from the core during reactor operation and inserted into the core only when the reactor is shut down, and so-called adjustment rods that are inserted into the reactor core even during operation and used for reactivity control. There are some things. The output of a unit cell (hereinafter referred to as a control cell) including control rods used as adjustment rods varies greatly depending on control rod operations during operation. Therefore, the thermal conditions of a fuel assembly within such a control cell are severe, and its health is adversely affected.
本発明は初めの１〜３サイクルの間に＃縮度が高い燃料
集合体が炉心から取ｐ出されることがなく、燃料の経済
性を向上し、また炉心の水平方向の出力分布を均一化す
るとともにコントロールセル内に装荷されている燃料集
合体の熱的条件を緩和し、燃料の健全性に悪影響を与え
ることがない沸騰水形原子炉の炉心を得ることにある。The present invention prevents fuel assemblies with a high degree of contraction from being removed from the core during the first 1 to 3 cycles, improving fuel economy and making the horizontal power distribution of the core more uniform. At the same time, it is an object of the present invention to provide a core for a boiling water reactor that does not adversely affect the integrity of the fuel by relaxing the thermal conditions of a fuel assembly loaded in a control cell.
本発明は炉心に装荷される燃料集合体を濃縮度の異なる
複数種類のものとし、最高濃縮度の燃料集合体を炉心の
最外周に装荷し、また最低濃縮度の燃料集合体をコント
ロールセル内に装荷したものである。したがって、兎１
サイクルの燃料交換時には最低濃縮度の燃料集合体を取
シ出して新燃料集合体と交換すれば、この最低濃縮度の
燃料集合体はもともと濃縮度が低いので１サイクル燃焼
しただけで取シ出されたとしてもその濃縮度は充分に低
下している。また、第２サイクルの燃料交換時には次に
濃縮度の低い燃料集合体を交換すればこれも充分に濃縮
度が低下した状態で取ｐ出される。よって以下同様に濃
縮度の低い願に燃料集合体を交換してゆけば濃縮度の高
い燃料集合体が炉心から取シ出されることはなく、燃料
の経済性が向上する。The present invention uses multiple types of fuel assemblies with different enrichments to be loaded into the reactor core, with the fuel assemblies with the highest enrichment being loaded on the outermost periphery of the core, and the fuel assemblies with the lowest enrichment being placed inside the control cells. It was loaded on. Therefore, rabbit 1
When replacing the fuel in a cycle, if you remove the fuel assembly with the lowest enrichment and replace it with a new fuel assembly, this fuel assembly with the lowest enrichment will be removed after just one cycle of combustion, since its enrichment is low to begin with. Even if it were, the concentration would be sufficiently reduced. Furthermore, during fuel exchange in the second cycle, if the next fuel assembly with a lower enrichment level is replaced, this fuel assembly will also be taken out in a sufficiently reduced enrichment state. Therefore, if fuel assemblies are replaced with fuel assemblies of lower enrichment in the same way, the fuel assemblies of higher enrichment will not be removed from the core, improving fuel economy.
また、最高濃縮度の燃料集合体すなわち無限増倍率の大
きな燃料集合体を炉心の最外周に装荷したので炉心の周
辺部の出力低下が少なく、炉心の水平方向の出力分布が
均一化される。また最低濃縮度の燃料集合体をコントロ
ールセル内に装荷したので、制御棒操作によ）このコン
トロールセルの出力が変動してももともとこの最低濃縮
度の燃料集合体は出力が低いので熱的条件は厳しくなら
ず、燃料の健全性に悪影響が生じることはない。Furthermore, since the fuel assembly with the highest enrichment level, that is, the fuel assembly with a large infinite multiplication factor, is loaded on the outermost periphery of the core, there is little reduction in the output at the periphery of the core, and the power distribution in the horizontal direction of the core is made uniform. In addition, since the fuel assembly with the lowest enrichment is loaded into the control cell, even if the output of this control cell changes due to control rod operation, the output of the fuel assembly with the lowest enrichment is originally low, so thermal conditions is not severe and fuel integrity is not adversely affected.
５−
〔発明の実施例〕
以下本発明の詳細な説明する。第１図ないし第３図は本
発明の第１実施例を示す。図中１・・・は制御棒であっ
て、この制御棒１・・・の周囲には４体の燃料集合体２
・・・が配置され、第１図に示す如き単位格子互を構成
している。そして、この単位格子互はその複数個が第２
図に示す如く格子状に配列され、第３図に示す如き炉心
！を構成している。なお、第３図では中央に制御棒１・
・・が記されたまず目のひとつがひとつの単位格子ｌ・
・・を示す。5- [Embodiments of the Invention] The present invention will be described in detail below. 1 to 3 show a first embodiment of the invention. In the figure, 1... is a control rod, and around this control rod 1... there are four fuel assemblies 2.
... are arranged to form a unit cell structure as shown in FIG. Then, this unit cell alternation is such that the plurality of units are the second
The reactor core is arranged in a lattice pattern as shown in the figure, and as shown in Figure 3! It consists of In addition, in Fig. 3, the control rod 1.
First of all, the unit cell l with one eye is marked...
...is shown.
そして、上記燃料集合体２・・・はウラン２３５の濃縮
度が互に異なる３種類のものが用いられている。この炉
心！は燃料交換の際に全燃料集合体２・・・（この実施
例では３６８体）のうちの約１／３の燃料集合体２・・
・を新燃料集合体と交換するように構成されている。そ
して、上記燃料集合体２・・・の種類数は上記１／３の
逆数すなわち３種類としたものである。そして、第１の
種類の燃料集合体２・−・は１［度が３．０％で、体数
は６−
１２０体である。また、第２の種類の燃料集合体２・・
・は濃縮度が２．２％で、体数は１２８体である。また
、第３の種類の燃料集合体２・・・は濃縮度が１．４％
で、体数は１２０体である。 ′そして、上記の各
種類の燃料集合体２・・・は第３図に示す如く装荷され
ている。なお、この第３図に記入された数字はその位置
に装荷される燃料集合体２・・・の種類を示すもので、
数字１は第１の種類、数字２は第２の種類、数字３は第
３の種類であることを示す。すなわち、上記第１の種類
す彦わち最高濃縮度の燃料集合体２・・社炉心！の最外
周の位置に装荷されている。また、第３の種類すなわち
最低濃縮度の燃料集合体２・・・はコントロールセル３
＊−（第３図中太線の四角で囲んで示す）内に装荷さ
れてｂる。また、第２の種類の燃料集合体２・・・およ
び最外周およヒ＝ｒ ｙ ） 日−ルセル３ ＊−・−
内に装荷できなかった残夛の第１および第３の種類の燃
料集合体２・・・は最外周を除く領域（第３図では破線
で囲んだ領域）内に装荷されている。そして、上記残少
の第１の種類の燃料集合体２・・・はコントロールセル
Ｑ・・・で挾まれた位置にある単位格子ｌ・・・内に装
荷され、また上記残夛の第３の種類の燃料集合体２・・
・はコントロールセルＤ・・・の対角位置にある単位格
子！・・・内に装荷されている。Three types of fuel assemblies 2 are used, each having a different enrichment degree of uranium-235. This core! is approximately 1/3 of the total fuel assemblies 2 (368 in this example) during fuel exchange.
・is configured to be replaced with a new fuel assembly. The number of types of fuel assemblies 2 is set to be the reciprocal of 1/3, that is, three types. The fuel assemblies 2 of the first type have a degree of 1[degrees] of 3.0%, and the number of fuel assemblies 2 is 6 to 120. In addition, a second type of fuel assembly 2...
・The enrichment level is 2.2%, and the number of bodies is 128. In addition, the third type of fuel assembly 2... has an enrichment level of 1.4%.
The number of bodies is 120. 'The various types of fuel assemblies 2 described above are loaded as shown in FIG. The numbers written in this Figure 3 indicate the type of fuel assembly 2... loaded at that position.
Number 1 indicates the first type, number 2 indicates the second type, and number 3 indicates the third type. In other words, the first type mentioned above, that is, the highest enrichment fuel assembly 2...the company core! It is loaded at the outermost position of the Further, the third type, that is, the fuel assembly 2 of the lowest enrichment... is the control cell 3.
*- (shown surrounded by a bold square in Figure 3). In addition, the second type of fuel assembly 2... and the outermost periphery and the outermost periphery and the fuel assembly 3 *--
The remaining fuel assemblies 2 of the first and third types that could not be loaded inside are loaded in the area excluding the outermost periphery (the area surrounded by the broken line in FIG. 3). Then, the remaining first type fuel assembly 2... is loaded into the unit grid l... located at a position sandwiched by the control cell Q..., and the remaining third type fuel assembly 2... Type of fuel assembly 2...
・is a unit cell at the diagonal position of control cell D...! ...is loaded inside.
次に上記第１実施例の作用を説明する。まず、第１サイ
クルの運転をおこなうと各燃料集合体２・・・は燃焼が
進み、濃縮度が低下する。そして、第１サイクルの運転
が終了したら第３の種類の燃料集合体２・・・を取シ出
し、代りに濃縮間３．０％の新燃料集合体２・・・を装
荷する。この場合、第３の種類の燃料集合体２・・・Ｕ
ｌサイクル燃焼しただけで炉心から取り出されるが、こ
の第３の種類の燃料集合体２・・・はもともと濃縮度が
低いので、炉心！から取シ出される際には濃縮度が充分
に低下しておシ、燃料の無駄が生じることはない。また
、炉心！の最外周には濃縮度の高い第１の種類の燃料集
合体２・・・が装荷されているので、炉心！の周辺部の
出方低下が抑えられ、炉心ｆの水平方向の出方分布が均
一化する。また、コントロールセルＬノ・・・内には濃
縮度が低い第３の種類の燃料集合体２・・・が装荷され
ているので、制御棒操作によって運転中にこのコントロ
ールセルＱ・・・の出力が変動しても、この第３の種類
の燃料集合体２・・・は出力が低いので熱的条件が厳し
くなることはなく、健全性に悪影響が生じることはない
。Next, the operation of the first embodiment will be explained. First, when the first cycle operation is performed, combustion progresses in each fuel assembly 2, and the enrichment level decreases. Then, when the first cycle operation is completed, the third type of fuel assembly 2 is taken out, and a new fuel assembly 2 with an enrichment period of 3.0% is loaded in its place. In this case, the third type of fuel assembly 2...U
Although it is removed from the core after just one cycle of combustion, this third type of fuel assembly 2... has a low enrichment level to begin with, so it is removed from the core! When the fuel is removed from the tank, the enrichment level is sufficiently reduced so that no fuel is wasted. Also, the reactor core! The first type of fuel assembly 2 with high enrichment is loaded on the outermost periphery of the reactor core! This suppresses the decline in the direction of outflow at the periphery of the reactor core f, and the horizontal outflow distribution of the core f becomes uniform. In addition, since a third type of fuel assembly 2 with a low enrichment level is loaded in the control cell L, this control cell Q is loaded during operation by control rod operation. Even if the output fluctuates, the third type of fuel assembly 2... has a low output, so the thermal conditions will not become severe, and the integrity will not be adversely affected.
また、炉心！の最外周に装荷しきれなかった残夛の第１
の種類の燃料集合体２・・・はコントロールセルＤ・・
・に挾まれた位置にある単位格子ｌ・・・すなわちコン
トロールセルＪ ａ −・−に最モ近い位置にある単位
格子互・・・内に装荷されており、またコントロールセ
ル８ａ・・・内に装荷し切れなかった第３の種類の燃料
集合体２・・・はコントロールセルＤ・・・の対角位置
にある単位格子！・・・すなわちコントロールセルＪａ
・・・から最も遠い位置にある巣位格子３＆・・・内に
装荷されているので、炉心ｆの出力分布が一層均一化さ
れる。Also, the reactor core! The first piece of debris that could not be loaded onto the outermost periphery of
The type of fuel assembly 2... is the control cell D...
・In other words, it is loaded in the unit cell l located in the position sandwiched between the control cells J a -...-, and in the control cell 8a... The third type of fuel assembly 2... that could not be fully loaded is the unit cell located diagonally to the control cell D...! ...In other words, control cell Ja
The power distribution of the core f is made even more uniform since it is loaded in the position grid 3 &... located at the farthest position from...
なお、１サイクルの燃焼によって、第２の種類の燃料集
合体２・・・はその濃＃度が第３の燃料９−
集合体２・・・の濃縮度と同程度に低下し、′また第１
の燃料集合体２・・・はその濃縮度が第２の種類の燃料
集合体と同程度まで低下する。したがって、新燃料集合
体の装荷の際に燃料集合体のシャラフリングをおこない
、第２の種類の燃料集合体２・・・を第３の種類の燃料
集合体２・・・のあった位置に装荷し、また第１の種類
の燃料集合体２・・・を第２の種類の燃料集合体２・・
・のあった位置に装荷し、さらに新燃料集合体を第１の
種類の燃料集合体２・・・のあった位置に装荷すれば最
初と同等の状態となる。以下同様にして第２回以降の燃
料交換をおこなう。In addition, by one cycle of combustion, the concentration of the second type of fuel assembly 2... decreases to the same degree as the enrichment of the third fuel assembly 2..., and 1st
The enrichment of the fuel assemblies 2... is reduced to the same level as that of the second type of fuel assemblies. Therefore, when loading a new fuel assembly, the fuel assembly is shuffled, and the second type of fuel assembly 2... is moved to the position where the third type of fuel assembly 2... was. The first type of fuel assembly 2... is loaded into the second type of fuel assembly 2...
If the new fuel assembly is loaded in the position where the fuel assembly 2 of the first type was located, the condition will be the same as the first one. Thereafter, the second and subsequent fuel exchanges are performed in the same manner.
なお、本発明は上記の第１実施例には限定されない。Note that the present invention is not limited to the first embodiment described above.
たとえばＭ４図には本発明の第２実施例を示す。この第
２実施例は各種類の燃料集合体の装荷領域を単位格子単
位とし、最外周の単位格子！・・・内にはすべて第１の
種類の燃料集合体を装荷し、またコントロールセルＤ・
・・内にハ第３の種類の燃料集合体を装荷し、またコン
トロー１０−
ルセル３ｇ・・・内に装荷しきれなかった第３の種類の
燃料集合体はコントロールセルＪａ・・・の対角位置に
ある単位格子ｌ・・・内に装荷したものである。For example, FIG. M4 shows a second embodiment of the present invention. In this second embodiment, the loading area of each type of fuel assembly is a unit cell, and the outermost unit cell! ... are loaded with fuel assemblies of the first type, and a control cell D.
The third type of fuel assembly is loaded in the control cell Ja..., and the third type of fuel assembly that could not be fully loaded in the control cell Ja... is loaded in the control cell Ja... It is loaded in a unit cell l located at a corner position.
また、第５図は本発明の第３実施例を示す。Further, FIG. 5 shows a third embodiment of the present invention.
この第３実施例は燃料交換の際に全燃料集合体の１／４
の燃料集合体を交換するように構成された炉心の場合で
あって、燃料集合体の種類数を１／４の逆数の４種類と
したものである。In this third embodiment, 1/4 of the total fuel assembly is used during fuel exchange.
This is a case where the core is configured to replace fuel assemblies, and the number of types of fuel assemblies is four, which is the reciprocal of 1/4.
上述の如く本発明は炉心に装荷される燃料集合体を濃縮
度の異なる複数種類のものとし、最高濃縮度の燃料集合
体を炉心の最外周に装荷し、また最低濃縮度の燃料集合
体をコントロールセル内に装荷したものである。したが
って、第１サイクルの燃料交換時には最低濃縮度の燃料
集合体を取シ出して新燃料集合体と交換すれに、この最
低濃縮度の燃料集合体はもともと濃縮度が低いので１サ
イクル燃焼しただけで取り出されたとしてもその濃縮度
は充分に低下している。As described above, the present invention uses multiple types of fuel assemblies with different enrichments to be loaded into the reactor core, with the fuel assemblies with the highest enrichment being loaded at the outermost periphery of the core, and the fuel assemblies with the lowest enrichment being loaded onto the outermost periphery of the core. It is loaded into the control cell. Therefore, at the time of fuel exchange in the first cycle, the fuel assembly with the lowest enrichment is taken out and replaced with a new fuel assembly, but since the fuel assembly with the lowest enrichment originally has a low enrichment, it has only been burned for one cycle. Even if it is taken out, its concentration is sufficiently reduced.
また、第２サイクルの燃料交換時には次に濃縮度の低い
燃料集合体を交換すればこれも充分に濃縮度が低下した
状態で取シ出される。よって以下同様に濃縮度の低い順
に燃料集合体を交換してゆけば濃縮度の高い燃料集合体
が炉心から取シ出されることはなく、燃料の経済性が向
上する。また、最高濃縮度の燃料集合体すなわち無限増
倍率の大きな燃料集合体を炉心の最外周に装荷したので
炉心の周辺部の出力低下が少なく、炉心の水平方向の出
力分布が均一化される。Furthermore, during fuel exchange in the second cycle, if the next fuel assembly with a lower enrichment level is replaced, this fuel assembly can also be taken out in a sufficiently reduced enrichment state. Therefore, if the fuel assemblies are replaced in descending order of enrichment in the same way, fuel assemblies with higher enrichment will not be removed from the core, and fuel economy will be improved. Furthermore, since the fuel assembly with the highest enrichment level, that is, the fuel assembly with a large infinite multiplication factor, is loaded on the outermost periphery of the core, there is little reduction in the output at the periphery of the core, and the power distribution in the horizontal direction of the core is made uniform.
また最低濃縮度の燃料集合体をコントロールセル内に装
荷したので、制御棒操作によりこのコントロールセルの
出力が変動してももともとこの最低濃縮度の燃料集合体
は出力が低いので熱的条件は厳しくならず、燃料の健全
性に悪影響が生じることはない等その効果は大である。In addition, since the fuel assembly with the lowest enrichment is loaded into the control cell, even if the output of this control cell changes due to control rod operation, the thermal conditions are severe because the output of the fuel assembly with the lowest enrichment is originally low. The effect is great, as there is no adverse effect on the integrity of the fuel.
第１図ないし第３図は本発明の第１実施例金示し、第１
図は単位格子の平面図、第２図は炉心の一部の平面図、
第３図は炉心の模式的な平面図である。第４図は第２夾
施例の炉心の模式的な平面図、第５図は第３実施例の炉
心の模式的な平面図である。
Ｊ・・・制御棒、２・・・燃料集合体、互・・・単位格
子、ｑ−」・・・コントロールセル（調整棒として使用
される制御棒を含んだ単位格子）、！・・・炉心。
出願人代理人 弁理士 鈴 江 武 彦１３−1 to 3 illustrate a first embodiment of the present invention;
The figure is a plan view of the unit cell, Figure 2 is a plan view of a part of the core,
FIG. 3 is a schematic plan view of the core. FIG. 4 is a schematic plan view of the reactor core of the second embodiment, and FIG. 5 is a schematic plan view of the reactor core of the third embodiment. J...Control rod, 2...Fuel assembly, Mutual...Unit cell, q-''...Control cell (unit cell containing control rods used as adjustment rods),! ...Reactor core. Applicant's agent Patent attorney Takehiko Suzue 13-
Claims (3)
格子を構成し、この単位格子を複数個格子状に配列して
炉心を構成したものにおいて、上記燃料集合体を濃縮度
の互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ゞ含む単位格子に
装荷したことを特徴とする沸騰水形原子炉の炉心。(1) In a system in which four fuel assemblies are arranged around a control rod to form a unit cell, and a reactor core is constructed by arranging a plurality of these unit cells in a lattice pattern, the fuel assemblies are The fuel assemblies with the highest enrichment were loaded at the outermost position of the core, and the fuel assemblies with the lowest enrichment were loaded into a unit grid containing control rods used as adjustment rods. A boiling water reactor core characterized by:
集合体と交換される燃料集合体の数を全燃料集合体のｌ
／ＮとしたときＮ種類であることを特徴とする特許 の沸騰水形原子炉の炉心。(2) The number of types of fuel assemblies is the number of fuel assemblies that are replaced with new fuel assemblies during fuel exchange.
A core of a patented boiling water reactor characterized by having N types when /N.
合体以外の残シの最高濃縮度の燃料集合体は調整棒とし
て使用される制御棒を含む単位格子の間にはさまれた位
置にある単位格子内に装荷され、また前記調整棒として
使用される制御棒を含む単位格子内に装荷された最低濃
縮度の燃料集合体以外の残シの最低濃縮度の燃料集合体
は調整棒として使用される制御棒を含む単位格子の対角
位置にある単位格子内に装荷されていることを特徴とす
る前記特許請求の範囲第１項記載の沸騰水形原子炉の炉
心。(3) The remaining fuel assemblies with the highest enrichment other than the fuel assemblies with the highest enrichment loaded on the outermost periphery of the core are sandwiched between unit cells containing control rods used as adjustment rods. The remaining fuel assemblies with the lowest enrichment other than the fuel assemblies with the lowest enrichment loaded in the unit cell at the position and the fuel assemblies with the lowest enrichment loaded in the unit cell containing the control rods used as the adjustment rods are adjusted. 2. The core of a boiling water nuclear reactor according to claim 1, wherein the core is loaded in a unit cell located diagonally to a unit cell containing control rods used as control rods.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57125350A JPS5915888A (en) | 1982-07-19 | 1982-07-19 | Bwr type reactor core |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57125350A JPS5915888A (en) | 1982-07-19 | 1982-07-19 | Bwr type reactor core |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5915888A true JPS5915888A (en) | 1984-01-26 |
Family
ID=14907943
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57125350A Pending JPS5915888A (en) | 1982-07-19 | 1982-07-19 | Bwr type reactor core |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5915888A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2015059737A1 (en) | 2013-10-21 | 2015-04-30 | 株式会社日立製作所 | Nuclear reactor core |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5570792A (en) * | 1978-10-19 | 1980-05-28 | Gen Electric | Method of charging and operating fuel in reactor core |
| JPS5622989A (en) * | 1979-08-01 | 1981-03-04 | Tokyo Shibaura Electric Co | Nuclear reactor |
-
1982
- 1982-07-19 JP JP57125350A patent/JPS5915888A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5570792A (en) * | 1978-10-19 | 1980-05-28 | Gen Electric | Method of charging and operating fuel in reactor core |
| JPS5622989A (en) * | 1979-08-01 | 1981-03-04 | Tokyo Shibaura Electric Co | Nuclear reactor |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2015059737A1 (en) | 2013-10-21 | 2015-04-30 | 株式会社日立製作所 | Nuclear reactor core |
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