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JPH0345357B2 - - Google Patents
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JPH0345357B2 - - Google Patents

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Publication number
JPH0345357B2
JPH0345357B2 JP56192275A JP19227581A JPH0345357B2 JP H0345357 B2 JPH0345357 B2 JP H0345357B2 JP 56192275 A JP56192275 A JP 56192275A JP 19227581 A JP19227581 A JP 19227581A JP H0345357 B2 JPH0345357 B2 JP H0345357B2
Authority
JP
Japan
Prior art keywords
fuel
cycle
old
core
units
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
JP56192275A
Other languages
Japanese (ja)
Other versions
JPS5892985A (en
Inventor
Yoshitaka Nakajima
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 JP56192275A priority Critical patent/JPS5892985A/en
Publication of JPS5892985A publication Critical patent/JPS5892985A/en
Publication of JPH0345357B2 publication Critical patent/JPH0345357B2/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
    • Y02E30/30Nuclear fission reactors

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

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の燃料を交換す
る際に適用される原子炉の燃料交換方法に関す
る。
DETAILED DESCRIPTION OF THE INVENTION Technical Field of the Invention The present invention relates to a nuclear reactor refueling method applied when exchanging fuel in a core of a boiling water nuclear reactor.

発明の技術的背景とその問題点 沸騰水形原子炉の炉心は、基本的には第1図に
示すように1本の断面十字状をなす制御棒aの回
りに4体1組の燃料集合体bを配置してなる燃料
単位cを炉心の平面方向に多数配列したものであ
り、たとえば80万kw級原子炉の炉心の平面形状
は第2図に示されるようなものである。同第2図
において斜線を施した部分は炉心の略1/4領域で
あつて、残りの3/4の領域はこの1/4領域と対称で
あるため、以下この斜線を施した1/4領域を代表
して説明する。
Technical background of the invention and its problems The core of a boiling water reactor basically consists of a set of four fuel assemblies surrounding one control rod a having a cross-shaped cross section, as shown in Figure 1. A large number of fuel units c each having bodies b arranged therein are arranged in the planar direction of the reactor core. For example, the planar shape of the core of an 800,000 kw class nuclear reactor is as shown in FIG. The shaded area in Figure 2 is approximately 1/4 area of the reactor core, and the remaining 3/4 area is symmetrical to this 1/4 area. I will explain on behalf of the area.

上記燃料集合体(以下単に燃料と称する)は通
常の約1年を1サイクルとして4サイクル分つま
り約4年間炉心に滞在されるが、各サイクルごと
に燃焼度が異なるために出力ピーキングの低減と
燃料経済性の向上を目的として、1サイクル終了
による燃料交換時に各燃料の配置換え(シヤツフ
リング)を行なつている。第3図は従来の典型的
な燃料の動きを示すものであり、の位置に装荷
された新燃料は2サイクル目にはの位置に移さ
れ、さらに3サイクル目にはの位置、4サイク
ル目にはの位置に移されてサイクル終了後、炉
心から取り去られる。
The above-mentioned fuel assembly (hereinafter simply referred to as fuel) stays in the core for four cycles, or about four years, with one normal cycle being about one year, but because the burnup differs for each cycle, the output peaking may be reduced. In order to improve fuel economy, each fuel is rearranged (shuffling) when replacing fuel at the end of one cycle. Figure 3 shows a typical conventional fuel movement. New fuel loaded at position is moved to position in the second cycle, then moved to position in the third cycle, and moved to position in the fourth cycle. After the cycle is completed, it is removed from the core.

このように従来は、各サイクルごとの燃料交換
時に炉心内のほぼ全数に及ぶ燃料を一度に移動さ
せているため、燃料の交換に要する時間が非常に
長くなり、定検期間の長期化を招き原子炉の稼動
率が低下する原因になつていた。
Conventionally, almost all of the fuel in the reactor core was moved at once during fuel exchange for each cycle, which resulted in a very long time for fuel exchange, leading to longer regular inspection periods. This was causing a decline in the reactor's operating rate.

また、従来の各燃料単位ごとに1サイクル目の
新燃料が通常1本含まれるように装荷している
が、第4図に示したように新燃料の方が、燃焼の
進んだ古い燃料よりも無限増倍率が高く反応度が
大きい。したがつて上記のように新燃料と2サイ
クル目以降の燃料が混在した燃料単位の場合、こ
れらの燃料が原子炉運転中に出力調整用として挿
入、引抜き操作される出力調整用制御棒の回りに
装荷されるものであると、出力運転中の制御棒の
引抜きあるいは挿入を行なう際には、線出力密度
の高い燃料の出力が急激に変化しないように、炉
心を低出力にした状態で制御棒操作を行なわざる
を得ず、稼動率損失が大きいという問題があつ
た。
Additionally, each unit of conventional fuel is loaded so that it usually contains one bottle of new fuel for the first cycle, but as shown in Figure 4, the new fuel is better than the older, more burnt-out fuel. also has a high infinite multiplication factor and high reactivity. Therefore, in the case of a fuel unit containing a mixture of new fuel and fuel from the second cycle onwards, as described above, these fuels are inserted into and pulled out for power adjustment during reactor operation around the power adjustment control rods. When the control rods are withdrawn or inserted during power operation, the core is controlled at low power to prevent sudden changes in the output of the fuel with high linear power density. There was a problem in that the operator had no choice but to operate the rod, resulting in a large loss in operating efficiency.

発明の目的 本発明は上記事情にもとづきなされたものでそ
の目的とするところは、燃料交換に要する時間を
短縮でき稼動率を向上できるとともに、出力調整
用制御棒まわりの燃料の線出力密度を低減するこ
とが可能となり、燃料経済性を向上できる原子炉
の燃料交換方法を提供することにある。
Purpose of the Invention The present invention was made based on the above circumstances, and its purpose is to shorten the time required for fuel exchange, improve operating efficiency, and reduce the linear power density of fuel around the control rods for power adjustment. It is an object of the present invention to provide a method for exchanging fuel in a nuclear reactor, which can improve fuel economy.

発明の概要 本発明の概要は以下述べるようなものである。
すなわち、炉心には3サイクル目の燃料のみから
なる3サイクル目燃料単位を原子炉の出力運転中
に出し入れ操作される出力調整用の制御棒位置に
配置するとともに、これら3サイクル目燃料単位
に対して縦横列方向には1サイクル目と2サイク
ル目の燃料からなる2種混合燃料単位を配置し、
かつ上記3サイクル目燃料単位に対して対角線方
向には1サイクル目と2サイクル目および3サイ
クル目の燃料からなる3種混合燃料単位を配置す
る。
Summary of the Invention The summary of the present invention is as follows.
That is, in the reactor core, 3rd cycle fuel units consisting only of 3rd cycle fuel are placed at control rod positions for power adjustment that are operated in and out during power operation of the reactor. Two types of mixed fuel units consisting of first cycle and second cycle fuel are arranged in the vertical and horizontal directions,
In addition, a three-type mixed fuel unit consisting of fuels for the first cycle, second cycle, and third cycle is arranged diagonally with respect to the third cycle fuel unit.

そして1サイクル終了ごとの燃料交換時には、
旧1サイクル目の燃料は移動させずにそのまま装
荷した状態にしておく。つまりこの燃料は次のサ
イクルでは2サイクル目の燃料となる。
And when changing fuel after each cycle,
The old first cycle fuel is left loaded without being moved. In other words, this fuel becomes the fuel for the second cycle in the next cycle.

また、旧2サイクル目の燃料は取り出してその
取り出した箇所に新燃料、すなわち1サイクル目
となる燃料を装荷する。
Further, the old second cycle fuel is taken out, and new fuel, that is, first cycle fuel, is loaded into the place where it was taken out.

さらに、旧3サイクル目の燃料は炉心から取り
去るかあるいは炉心周辺部に移動させるととも
に、その取り出した箇所に上記旧2サイクル目の
燃料、すなわち次に3サイクル目になる燃料を装
荷する。
Furthermore, the old third cycle fuel is removed from the core or moved to the core periphery, and the old second cycle fuel, that is, the fuel that will be the next third cycle, is loaded into the removed area.

上記本発明方法によれば、旧1サイクル目の燃
料は移動することなくその場で2サイクル目の燃
料となり、更に次のサイクルでは取出されて再び
1サイクル目の新燃料が装荷されることとなる。
換言すれば1サイクル目の燃料と2サイクル目の
燃料の位置関係は1サイクル終了ごとに交互に変
わるが、1サイクル目から2サイクル目に移る際
の燃料自体の位置は不動である。
According to the above-mentioned method of the present invention, the old fuel from the first cycle becomes fuel for the second cycle on the spot without being moved, and in the next cycle, it is taken out and new fuel from the first cycle is loaded again. Become.
In other words, the positional relationship between the fuel in the first cycle and the fuel in the second cycle changes alternately every time one cycle ends, but the position of the fuel itself remains unchanged when moving from the first cycle to the second cycle.

したがつて、燃料交換時に旧1サイクル目の燃
料を移す必要がないため、ほぼ全燃料を移動させ
ていた従来に比べて燃料移動数が大幅に減少し、
燃料交換に要する時間を短縮できる。
Therefore, there is no need to transfer the old 1st cycle fuel when changing fuel, so the number of fuel transfers is significantly reduced compared to the conventional method, in which almost all fuel was transferred.
The time required for fuel exchange can be shortened.

また、3サイクル目のみの燃料からなる3サイ
クル目燃料単位に出力調整用制御棒を配置させる
ことができるため、出力調整用制御棒まわりの燃
料の線出力密度を低減することが可能になるもの
である。
In addition, since the output adjustment control rod can be placed in the 3rd cycle fuel unit consisting of only the 3rd cycle fuel, it is possible to reduce the linear power density of the fuel around the output adjustment control rod. It is.

発明の実施例 以下本発明方法の一実施例について第5図およ
び第6図を参照して説明する。第5図は、あるサ
イクル中の燃料の配置を示すものであり、この炉
心には炉心外周部を除いた箇所に、3サイクル目
の燃料のみからなる3サイクル目燃料単位10…
(図面上に斜線を施した部分)を、複数箇所に配
置してある。これら3サイクル目燃料単位10…
は、原子炉の出力運転中に出力調整用として出し
入れ操作される制御棒すなわち出力調整用の制御
棒を設ける位置に対応して配置されていて、これ
ら3サイクル目燃料単位の少なくともいずれかに
出力調整用の制御棒が挿入されるようになつてい
る。
Embodiment of the Invention An embodiment of the method of the present invention will be described below with reference to FIGS. 5 and 6. FIG. 5 shows the arrangement of fuel during a certain cycle. In this core, there are 10 third cycle fuel units consisting only of third cycle fuel, excluding the outer periphery of the core.
(hatched areas on the drawing) are arranged at multiple locations. These 3rd cycle fuel units are 10...
are arranged corresponding to the position where the control rods for output adjustment, that is, the control rods for output adjustment are operated in and out for output adjustment during the output operation of the reactor. A control rod for adjustment is inserted.

また、これら3サイクル目燃料単位10…に対
して縦横列方向には、1サイクル目と2サイクル
目の燃料2体ずつからなる2種混合燃料単位11
…(図面上にて丸枠で囲んだ部分)が配置されて
いる。これら2種混合燃料単位11…は、炉心中
心Pに対して対称性を持たせるため、炉心中心P
に対して縦方向と横方向に並ぶものは同サイクル
の燃料2体が互いに隣接するように平行に並べ、
それ以外の2種混合燃料単位は同サイクルの燃料
2体が互いに対角線方向に並ぶようにしてある。
In addition, in the vertical and horizontal directions for these 3rd cycle fuel units 10..., there are 2 types of mixed fuel units 11 each consisting of 2 fuels for the 1st cycle and 2 fuels for the 2nd cycle.
...(the part surrounded by a circle on the drawing) is located. These two types of mixed fuel units 11... have symmetry with respect to the core center P.
In contrast, those arranged in the vertical and horizontal directions are arranged in parallel so that two fuel bodies of the same cycle are adjacent to each other,
In other two-type mixed fuel units, two fuels of the same cycle are arranged diagonally to each other.

これら2種混合燃料単位11…は、燃焼が進ん
で反応後の低下している3サイクル目燃料単位1
0…に隣接するように配置してあるから、上記の
ように反応度の高い1サイクル目燃料と2サイク
ル目燃料を各2体ずつ組合わせてあつても3サイ
クル目燃料単位10…によつて反応が抑制される
ため、このように反応度の高い燃料を組合わせて
も問題はない。
These two types of mixed fuel units 11... are the 3rd cycle fuel units 1 whose combustion has progressed and have decreased after the reaction.
Since they are arranged adjacent to 0..., even if two units each of the highly reactive 1st cycle fuel and 2nd cycle fuel are combined as described above, the 3rd cycle fuel unit 10... Since the reaction is suppressed, there is no problem even if such highly reactive fuels are combined.

さらに、上記3サイクル目燃料単位10…に対
して対角線方向には、1サイクル目と2サイクル
目および3サイクル目の燃料からなる3種混合燃
料単位12…(図面上にて点線の枠で囲んだ部
分)を配置してある。これら3種混合燃料単位1
2…は、2体の2サイクル目燃料を互いに対角線
方向に配置するとともに、1サイクル目と3サイ
クル目の燃料を各1体ずつ互いに対角線上に配置
したものである。
Furthermore, in the diagonal direction with respect to the third cycle fuel unit 10..., there is a three-type mixed fuel unit 12... (encircled by a dotted line frame in the drawing) consisting of the first, second, and third cycle fuels. ) are arranged. These three types of mixed fuel unit 1
2... is one in which two second-cycle fuels are arranged diagonally to each other, and one each of first-cycle and third-cycle fuels are arranged diagonally to each other.

また、図面上に太枠で囲つて示した炉心の最外
周部13には、主に4サイクル目の燃焼度の進ん
だ燃料と、3サイクル目の燃料の一部を配置して
ある。なお、上記外周部13の近傍位置の燃料は
従来と同様に配置されている。
Moreover, in the outermost peripheral part 13 of the core, which is shown surrounded by a bold frame in the drawing, fuel with a high burnup in the fourth cycle and a part of the fuel in the third cycle are mainly arranged. Note that the fuel near the outer peripheral portion 13 is arranged in the same manner as in the conventional case.

そして上記燃料配置で1サイクルが終了する
と、次に述べるように燃料交換が行なわれる。す
なわち第6図に示したように、2種混合燃料単位
11…および3種混合燃料単位12…において
は、旧1サイクル目の燃料は移動させずにそのま
ま装荷した状態にしておく。したがつて、第6図
に示すサイクルでは、旧1サイクル目の燃料はそ
のまま2サイクル目の燃料となる。
When one cycle is completed with the above fuel arrangement, fuel exchange is performed as described below. That is, as shown in FIG. 6, in the two-type mixed fuel units 11... and the three-type mixed fuel units 12..., the fuel from the previous first cycle is left loaded without being moved. Therefore, in the cycle shown in FIG. 6, the fuel used in the old first cycle becomes the fuel used in the second cycle.

また、第5図に示されている旧2サイクル目の
燃料は取り出して、その取り出した箇所に、第6
図に示したように新燃料、すなわち1サイクル目
となる燃料を装荷する。
Also, remove the old 2nd cycle fuel shown in Figure 5 and place it in the 6th cycle where it was taken out.
As shown in the figure, new fuel, that is, fuel for the first cycle, is loaded.

すなわち、上記の動作により、1サイクル目の
燃料と2サイクル目の燃料の位置関係は逆にな
る。
That is, due to the above operation, the positional relationship between the fuel in the first cycle and the fuel in the second cycle is reversed.

さらに、第5図に示されている旧3サイクル目
の燃料は、炉心から取り去るかあるいは炉心外周
部13の旧4サイクル目の燃料の位置に移し換え
る。そして旧3サイクル目の燃料を取り出した箇
所には、上記した旧2サイクル目の燃料、つまり
次サイクルでは3サイクル目になる燃料が装荷さ
れる。
Further, the old third cycle fuel shown in FIG. 5 is removed from the core or transferred to the position of the old fourth cycle fuel in the core outer periphery 13. Then, the above-mentioned old second cycle fuel, that is, the fuel for the third cycle in the next cycle, is loaded into the location where the old third cycle fuel was taken out.

したがつて、第6図に示されるように3サイク
ル目の燃料の位置は見かけ上は変わらず、前回の
サイクルと同様に3サイクル目燃料単位10…と
3種混合燃料単位12…では同じ位置に3サイク
ル目の燃料が位置することになる。
Therefore, as shown in Fig. 6, the position of the fuel in the third cycle does not appear to change, and as in the previous cycle, the position of the fuel unit 10 of the third cycle and the three-type mixed fuel unit 12 are the same. The fuel for the third cycle will be located at .

なお、3種混合燃料単位12…においては、第
6図に示した燃料配置では各単位ごとに2体の新
燃料を含むことになるが、これら燃料単位には必
らず3サイクル目の燃料が含まれるため、このよ
うに反応度の高い燃料を組合わせることが可能で
ある。
In addition, in the three-type mixed fuel units 12..., each unit contains two pieces of new fuel in the fuel arrangement shown in Fig. 6, but these fuel units do not necessarily contain the fuel in the third cycle. It is possible to combine fuels with high reactivity in this way.

そして上記の燃料配置で原子炉を稼動し、1サ
イクルすなわち1年ないし1.5年運転後、再び上
記方法で燃料交換を行なう。すなわち次サイクル
では再び第5図に示された燃料配置となるもので
ある。
Then, the reactor is operated with the above fuel arrangement, and after one cycle, ie, 1 to 1.5 years of operation, the fuel is replaced again using the above method. That is, in the next cycle, the fuel arrangement shown in FIG. 5 will be used again.

しかして上記実施例方法によれば、炉心の外周
部近傍を除いた炉心中心部では燃料交換時に旧1
サイクル目の燃料は移動させずに済むため、その
分だけ燃料交換の手間が省ける。すのわち従来は
新燃料以外もほぼ全数移動させていたのに対し、
上記方法によれば新燃料以外の移動数が半数以下
に減るため、燃料交換に要する時間が大幅に短縮
される。
However, according to the method of the above embodiment, in the center of the core except for the vicinity of the outer periphery of the core, the old
Since the fuel for the first cycle does not need to be moved, the effort of replacing the fuel can be saved accordingly. Whereas previously, almost all fuel other than new fuel was moved,
According to the above method, the number of transfers of fuel other than new fuel is reduced to less than half, so the time required for fuel exchange is significantly shortened.

しかも出力調整用制御棒が挿入される燃料単位
を、全て3サイクル目燃料で構成したため、燃料
の線出力密度は制御棒全引抜き時でも10kW/ft
以下であり、従来のように新燃料が含まれていた
場合に比べて約2kW/ft低減された。したがつ
て、原子炉出力調整時の制御棒操作を80〜90%の
高出力の状態で行なうことができるため、従来の
ように50〜60%まで出力を下げて制御棒操作を行
なつていた場合に比べて、稼動率損失が2〜3%
低減できるものである。
Moreover, since the fuel unit into which the output adjustment control rods are inserted is entirely composed of 3rd cycle fuel, the linear power density of the fuel is 10kW/ft even when the control rods are completely withdrawn.
This is approximately 2kW/ft lower than when new fuel was included as before. Therefore, control rod operations during reactor power adjustment can be performed at a high power of 80 to 90%, instead of operating control rods with the power reduced to 50 to 60% as in the past. The operating rate loss is 2-3% compared to the case where
This can be reduced.

発明の効果 本発明は前記したように、炉心外周部近傍を除
いた炉心部において1サイクル目の燃料は燃料交
換時に移動させずに済むようにしたものであるか
ら、燃料交換に要する時間を短縮でき定検期間の
短縮によつて原子炉の稼動率を向上させることが
できる。また、3サイクル目の燃料のみからなる
燃料単位に出力調整用制御棒を位置させることも
可能となり、この場合には出力調整用制御棒まわ
りの燃料の線出力密度を低減させることができる
ので、従来のように出力調整時に大幅に低出力に
した状態で制御棒操作を行なわずに済むことか
ら、稼動率損失を低減できるなど、稼動率を向上
させる上で大きい効果がある。
Effects of the Invention As described above, the present invention eliminates the need to move the first cycle fuel in the core except for the vicinity of the outer periphery of the core during fuel exchange, thereby reducing the time required for fuel exchange. By shortening the regular inspection period, the operating rate of the reactor can be improved. It is also possible to position the output adjustment control rod in a fuel unit consisting only of fuel in the third cycle, and in this case, the linear power density of the fuel around the output adjustment control rod can be reduced. Since there is no need to operate the control rods at a significantly lower output during output adjustment as in the past, this system has great effects in improving the operating rate, such as reducing operating rate losses.

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

第1図は燃料集合体と制御棒の位置関係を示す
燃料単位の概略平面図、第2図は炉心の形状を示
す概略平面図、第3図は従来の燃料の動きを示す
概略図、第4図は燃料の無限増倍率の変化を示す
図、第5図および第6図はそれぞれ本発明方法に
よる燃料交換の前後の状態を示す炉心の一部の燃
料配置図である。 a……制御棒、b……燃料集合体(燃料)、1
0……3サイクル目燃料単位、11……2種混合
燃料単位、12……3種混合燃料単位、13……
炉心最外周部。
Figure 1 is a schematic plan view of a fuel unit showing the positional relationship between fuel assemblies and control rods, Figure 2 is a schematic plan view showing the shape of the core, Figure 3 is a schematic diagram showing the movement of conventional fuel, FIG. 4 is a diagram showing changes in the infinite multiplication factor of fuel, and FIGS. 5 and 6 are fuel arrangement diagrams of a part of the reactor core, respectively, showing the states before and after fuel exchange according to the method of the present invention. a... Control rod, b... Fuel assembly (fuel), 1
0...3rd cycle fuel unit, 11...2 type mixed fuel unit, 12...3 type mixed fuel unit, 13...
The outermost part of the core.

Claims (1)

【特許請求の範囲】[Claims] 1 1本の制御棒の回りに4体1組の燃料集合体
を配置してなる燃料単位を多数配列して炉心を構
成し、この炉心には3サイクル目の燃料のみから
なる3サイクル目燃料単位を原子炉の出力運転中
に出し入れ操作される出力調整用の制御棒位置に
配置するとともに、これら3サイクル目燃料単位
に対して縦横列方向には1サイクル目と2サイク
ル目の燃料からなる2種混合燃料単位を配置し、
かつ上記3サイクル目燃料単位に対して対角線方
向には1サイクル目と2サイクル目および3サイ
クル目の燃料からなる3種混合燃料単位を配置
し、1サイクル終了による燃料交換時には、旧1
サイクル目の燃料は移動させずにそのままの位置
に装荷しておき、また旧2サイクル目の燃料は取
り出してその取り出した箇所に新燃料を装荷し、
さらに旧3サイクル目の燃料は炉心から取り去る
かあるいは炉心周辺部に移動させるとともに、そ
の取り出した箇所に上記旧2サイクル目の燃料を
装荷することを特徴とする原子炉の燃料交換方
法。
1. A reactor core is constructed by arranging a large number of fuel units each consisting of a set of four fuel assemblies arranged around one control rod, and this core contains third-cycle fuel consisting only of third-cycle fuel. The unit is placed at the position of the control rod for power adjustment that is operated in and out during the output operation of the reactor, and the fuel units of the 1st cycle and the 2nd cycle are arranged in the vertical and horizontal directions relative to these 3rd cycle fuel units. Arrange two types of mixed fuel units,
In addition, a three-type mixed fuel unit consisting of fuel from the first cycle, second cycle, and third cycle is arranged diagonally with respect to the third cycle fuel unit, and when replacing the fuel at the end of one cycle, the old one
The fuel for the first cycle is loaded in the same position without being moved, and the old fuel for the second cycle is taken out and new fuel is loaded in the place where it was taken out.
Furthermore, the method for replacing fuel in a nuclear reactor is characterized in that the old third cycle fuel is removed from the reactor core or moved to the periphery of the reactor core, and the old second cycle fuel is loaded into the removed area.
JP56192275A 1981-11-30 1981-11-30 Method of exchanging fuel of nuclear reactor Granted JPS5892985A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56192275A JPS5892985A (en) 1981-11-30 1981-11-30 Method of exchanging fuel of nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56192275A JPS5892985A (en) 1981-11-30 1981-11-30 Method of exchanging fuel of nuclear reactor

Publications (2)

Publication Number Publication Date
JPS5892985A JPS5892985A (en) 1983-06-02
JPH0345357B2 true JPH0345357B2 (en) 1991-07-10

Family

ID=16288560

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56192275A Granted JPS5892985A (en) 1981-11-30 1981-11-30 Method of exchanging fuel of nuclear reactor

Country Status (1)

Country Link
JP (1) JPS5892985A (en)

Also Published As

Publication number Publication date
JPS5892985A (en) 1983-06-02

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