JPH01304387A - Fuel assembly for nuclear reactor - Google Patents

Fuel assembly for nuclear reactor

Info

Publication number
JPH01304387A
JPH01304387A JP63132645A JP13264588A JPH01304387A JP H01304387 A JPH01304387 A JP H01304387A JP 63132645 A JP63132645 A JP 63132645A JP 13264588 A JP13264588 A JP 13264588A JP H01304387 A JPH01304387 A JP H01304387A
Authority
JP
Japan
Prior art keywords
fuel
gadolinia
enrichment
parts
decreased
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
JP63132645A
Other languages
Japanese (ja)
Other versions
JP2723252B2 (en
Inventor
Kazutaka Hida
和毅 肥田
Ritsuo Yoshioka
律夫 吉岡
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 Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
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 Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP63132645A priority Critical patent/JP2723252B2/en
Publication of JPH01304387A publication Critical patent/JPH01304387A/en
Application granted granted Critical
Publication of JP2723252B2 publication Critical patent/JP2723252B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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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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  • Spray-Type Burners (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To improve fuel economy by maintaining low enrichment at the top end or bottom end of fuel, thereby decreasing the residual amt. of gadolinia at the top and bottom ends of the fuel at the end period of an operation cycle as far as possible and concentrating the output to the center of the reactor core. CONSTITUTION:This fuel assembly is constituted by further dividing the central high enrichment part in the axial direction of the fuel and decreasing the number of the gadolinia in the part adjacent to the low enrichment parts at the top and bottom ends to lower the enrichment. The residual amt. of gadolinia where the residual amt. of gadolinia is high is decreased by this fuel. Further, the central part adjacent to the parts where the loading amt. of the gadolinia is decreased burns most in follow up to the combustion of the parts where the loading amt. of the gadolinia is decreased and, therefore, the residual amt. of the gadolinia is decreased in any parts of the fuel. Since the combustion at the top and bottom ends and the parts adjacent thereto progresses most, the output distribution at the end period of the cycle is more concentrated and distributed to the center. As a result, the average enrichment of the fuel assembly is decreased and the output is concentrated more to the center of the core. The fuel economy is thus improved.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は燃料経済性をできるだけ高めるようにした原子
炉用燃料集合体に関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Field of Application) The present invention relates to a fuel assembly for a nuclear reactor, which is designed to maximize fuel economy.

(従来の技術) 従来の原子炉用燃料集合体では、燃料集合体を構成する
各燃料棒に装荷された核分裂性物質の濃縮度は軸方向に
おいて均一であった。
(Prior Art) In a conventional fuel assembly for a nuclear reactor, the degree of enrichment of the fissile material loaded in each fuel rod constituting the fuel assembly was uniform in the axial direction.

ところが、ウラン資源を節約するために、一定出力を得
るに必要なウラン燃料をできるだけ少量化するいわゆる
燃料経済性の問題が提起され、近年これに対処して核分
裂性物質の濃縮度を燃料棒の上端および下端において中
央部より低下させて軸方向に濃縮度分布をもたせ、上下
端からの中性子の漏れを低減させることによって燃料経
済性を向上させることのできる燃料集合体か提案されて
いる(例えば特開昭59−38684号)。
However, in order to conserve uranium resources, the problem of so-called fuel economy has been raised, in which the amount of uranium fuel required to obtain a certain output is reduced as much as possible. A fuel assembly has been proposed that can improve fuel economy by reducing neutron enrichment distribution in the axial direction by lowering the concentration at the upper and lower ends than in the center and reducing leakage of neutrons from the upper and lower ends (e.g. JP-A No. 59-38684).

核分裂性物質の濃縮度が均一である従来例(以下従来例
1と称す)を第4図に、また、上下端の濃縮度が中央部
よりも低い従来例(以下従来例2と称す)を第5図に示
す。これら従来例は何れも初装荷用燃料であり、軸方向
出力ビーキングをある設定値(本例では1.4)以下に
抑えるために、燃料上下で可燃性毒物であるガドリニア
装荷量を異ならせている。両図から分るとおり、燃料棒
の上下端を低濃縮の天然ウランとすることによって、燃
料集合体平均の濃縮度を低くすることができ、従来例2
では従来例1に比べて約4%のウラン資源節約効果が得
られている。
Figure 4 shows a conventional example in which the degree of enrichment of fissile material is uniform (hereinafter referred to as conventional example 1), and a conventional example in which the degree of enrichment at the upper and lower ends is lower than in the center (hereinafter referred to as conventional example 2). It is shown in FIG. All of these conventional examples are fuels for initial loading, and in order to suppress the axial output peaking to a certain set value (1.4 in this example) or less, the loading amount of gadolinia, which is a burnable poison, is varied between the upper and lower portions of the fuel. There is. As can be seen from both figures, by using low-enriched natural uranium at the upper and lower ends of the fuel rods, the average enrichment of the fuel assembly can be lowered, compared to conventional example 2.
Compared to Conventional Example 1, a uranium resource saving effect of about 4% is obtained.

(発明が解決しようとする課題) しかしながら、従来例2にd3いても未だ燃料経済性の
向上の余地が残されていることが判明した。
(Problems to be Solved by the Invention) However, it has been found that even with d3 in Conventional Example 2, there is still room for improvement in fuel economy.

これを示すためにサイクル末期のガドリニア残留量を第
6図に示ず。ガドリニアは、制御棒とともに燃料の反応
度をコン1〜ロールして炉心を臨界に維持する制御材で
あるが、これがサイクル末期まで残っていると、反応度
を低下させ運転期間を短くすることになる。従来例1に
おけるガドリニア残留量は、第6図(a)に示されると
おり、燃料集合体上上端で顕著である。これに対して、
従来例2では上下端低濃縮部にはガドリニアを装荷し。
To illustrate this, the amount of gadolinia remaining at the end of the cycle is not shown in FIG. Gadolinia, together with the control rods, is a control material that controls the reactivity of the fuel and maintains the reactor core at a critical level, but if it remains until the end of the cycle, it will reduce the reactivity and shorten the operating period. Become. The residual amount of gadolinia in Conventional Example 1 is significant at the upper end of the fuel assembly, as shown in FIG. 6(a). On the contrary,
In conventional example 2, gadolinia is loaded in the upper and lower end low concentration sections.

ていないので、従来例1におけるガドリニア残留の大部
分が無くなり、この意味でも経済性向上の効果かあると
期待された。
Therefore, most of the remaining gadolinia in Conventional Example 1 was eliminated, and in this sense, it was expected that there would be an effect of improving economic efficiency.

ところか、第6図(b)に示されているとおり、従来例
2では、上下端低濃縮部に隣接する部分に多量のガドリ
ニアが残留することが判明した。その理由は第7図に示
したサイクル末期の燃焼度分布から分かる。すなわち、
従来例2では上下端を低濃縮としたために、その部分の
みならず、隣接部分までも燃焼が遅れてしまうからでお
る。
However, as shown in FIG. 6(b), in Conventional Example 2, it was found that a large amount of gadolinia remained in the portions adjacent to the upper and lower end low concentration portions. The reason for this can be seen from the burnup distribution at the end of the cycle shown in FIG. That is,
In Conventional Example 2, since the upper and lower ends are low enriched, combustion is delayed not only in those parts but also in the adjacent parts.

第7図に示したサイクル末期燃焼度分イt、は、さらに
改善の余地がおることを示している。第7図のように燃
焼した結果、サイクル末期の出力分布は第8図のように
なる。すなわち、従来例2では従来例1に比べて、上下
端を低濃縮としたことによって上下端の出力か低下し、
相対的に出力か炉心の中央に集中した分布となっており
、これによっても燃料経済性が改善されている。しかし
ながら、従来例2では従来例1に比べて、上下端部おJ
:びこれに隣接する部分の燃焼か不充分であるが1、こ
れかもし従来例1並みであれば一す−イクル末期の出力
はより一層中央に集中した形となり、さらに燃料経済性
向上の可能性がある。
The burn-up at the end of the cycle shown in FIG. 7 shows that there is still room for further improvement. As a result of combustion as shown in FIG. 7, the output distribution at the end of the cycle becomes as shown in FIG. 8. That is, in Conventional Example 2, compared to Conventional Example 1, the output at the upper and lower ends is lower due to the lower concentration at the upper and lower ends.
The power output is relatively concentrated in the center of the core, which also improves fuel economy. However, in conventional example 2, compared to conventional example 1, the upper and lower ends are
:The combustion in the adjacent part is insufficient, but if this is the same as the conventional example 1, the output at the end of the cycle will be more concentrated in the center, and there is a possibility of further improving fuel economy. be.

本発明は上記事情に鑑みてなされたもので、その目的は
運転サイクル末期における燃料上下端部分のガドリニア
残留量を極力低減し、さらに出力を炉心中央により集中
させて燃料経済性を向上するようにした原子炉用燃料集
合体を提供することにある。
The present invention was made in view of the above circumstances, and its purpose is to reduce as much as possible the amount of gadolinia remaining in the upper and lower ends of the fuel at the end of the operating cycle, and to further concentrate the power in the center of the reactor core to improve fuel economy. An object of the present invention is to provide a fuel assembly for a nuclear reactor.

[発明の構成] (課題を解決するためめ手段) 本発明は、上記目的を達成するために、複数本の燃料棒
を格子状に配列して構成される原子用燃料集合体におい
て、燃料集合体の下端部おるいは下端部の少なくとも一
方の核分裂物質含有量が当該燃料集合体の他の部分の核
分裂物質含有量よりも少なく、しかも、前記核分裂物質
含有量の少ない上端部あるいは下端部およびこれらのう
ち少なくとも一方に隣接する部分の可燃性毒物含有量が
他の部分よりも小さいかまたはこれらの部分には装荷さ
れていないことを特徴とするものでおる。
[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention provides a fuel assembly in a nuclear fuel assembly configured by arranging a plurality of fuel rods in a lattice shape. The content of fissile material in the lower end or at least one of the lower ends of the fuel assembly is lower than the content of fissile material in other parts of the fuel assembly; It is characterized in that the content of the burnable poison in a portion adjacent to at least one of these portions is smaller than that in the other portions, or that the burnable poison is not loaded in these portions.

(作 用) 本発明によれば、燃料の上端部あるいは下端部を低濃縮
度としたことによって中性子の炉心外へ= 5 = の漏れが減少し、ざらに、上端部あるいは下端部および
これらに隣接する領域にあける可燃性毒物の装荷量を他
の領域よりも小さくするかまたは装荷しないことによっ
てこれらの領域の燃焼を促進させ、もってサイクル末期
のガドリニア残留量を燃料全体にわたって低減すると同
時に炉心中央に出力を集中させることができるので、燃
料経済性を向上させることができる。
(Function) According to the present invention, the leakage of neutrons to the outside of the reactor core is reduced by making the upper end or the lower end of the fuel have a low enrichment level, and the leakage of neutrons to the outside of the reactor core is generally reduced. By reducing the loading amount of burnable poison in adjacent areas compared to other areas or not loading it, combustion in these areas is promoted, thereby reducing the amount of gadolinia remaining at the end of the cycle throughout the fuel, and at the same time reducing the amount of burnable poison in the center of the core. Since the output can be concentrated in the fuel economy, fuel economy can be improved.

(実施例) 本発明の実施例を図面を参照して説明する。(Example) Embodiments of the present invention will be described with reference to the drawings.

第1図は本発明の第1の実施例の燃料の軸方向の濃縮度
・ガドリニア分布図である。
FIG. 1 is an axial enrichment/gadolinia distribution diagram of fuel according to a first embodiment of the present invention.

本実施例では、第5図の従来例2における中央高濃縮部
分をさらに分割し、上下端の低濃縮部に隣接する部分に
おいてガドリニア本数を少なく濃縮度を低くした構成と
している。このような燃料によると、従来例2において
ガドリニア残留量の多かった部分のガドリニア残留量を
少なくすることかできる。さらに、従来例1と従来例2
との比較から類推すれば、本実施例ではガドリニア装荷
市を少なくした部分に隣接する中央部分において再びノ
ットリニア残留量か増加することが予測されるか、第7
図に示すようにカドリニア装荷量を少ナクシた部分の燃
焼に引きずられてこの部分もよく燃焼するので、燃)5
1のどの部分においてもカドリニア残留量を低減するこ
とかできる。また、従来例2に比べて」1下端部d″3
よびこれに隣接する部分の燃焼がよく進行する結果、1
ノ−イクル末期の出ツノ分布は第8図のようにより一層
中央に集中した分布となる。これらの結果、燃料集合体
平均の濃縮度を低減することかでき、従来例2に対して
約3%、従来例1に対しては約7%のウラン資源か節約
できた。
In this embodiment, the central highly enriched portion in Conventional Example 2 shown in FIG. 5 is further divided, and the number of gadolinia is reduced and the concentration is lowered in the portions adjacent to the lower enriched portions at the upper and lower ends. According to such a fuel, the amount of gadolinia remaining in the portion where the amount of remaining gadolinia was large in Conventional Example 2 can be reduced. Furthermore, conventional example 1 and conventional example 2
By analogy, in this example, it is predicted that the not-linear residual amount will increase again in the central part adjacent to the part where the gadolinia loading city is reduced.
As shown in the figure, this part also burns well due to the combustion of the part with a small amount of cadrinia loaded, so the fuel)
It is possible to reduce the amount of residual cadrinia in any part of 1. In addition, compared to conventional example 2, "1 lower end d"3
As a result of the combustion progressing well in the area and adjacent areas, 1
The distribution of the horns at the end of the no-cycle becomes more concentrated in the center as shown in FIG. As a result, the average enrichment of the fuel assembly could be reduced, and uranium resources could be saved by about 3% compared to Conventional Example 2 and by about 7% compared to Conventional Example 1.

各領域の長さは上端部では燃料全長の3/24以下、下
端部ては2/24以下、また、これらに隣接する領域は
上部で3/24以下、下部で2/24以下か適当である
The length of each region is 3/24 or less of the total fuel length at the upper end, 2/24 or less at the lower end, and the length of the adjacent region is 3/24 or less at the top and 2/24 or less at the bottom, or as appropriate. be.

第2図は本発明の第2の実施例の燃料の軸方向の濃縮度
・カドリニア分イ11図である。
FIG. 2 is an 11 diagram showing the axial enrichment/cadrinier fraction of fuel according to the second embodiment of the present invention.

本実施例では、燃料の上下端の天然ウラン部に隣接する
部分にカドリニアを装荷していない。しかし、このまま
ではこの領域の出ツノピーキングか制限値を越えてしま
うので、この部分の濃縮度を中央部よりも低くしている
In this example, cadrinia is not loaded in the upper and lower ends of the fuel adjacent to the natural uranium portions. However, if left as is, the peaking in this area would exceed the limit value, so the concentration level in this area is set lower than in the central area.

下記第1および第2実施例では出力ビーキングを抑制す
るために、中央部を丁度真中で上下に分割し、下部より
多くのガドリニアを装荷したか、上下に分割する位置は
この(=j近でおれば必ずし′しこの位置に限定されな
い。また、別の手段として上部の濃縮度を高くしたり、
あるいは濃縮度差とガドリニア差の組合ぜを用いること
もできる。
In the first and second embodiments below, in order to suppress output beaking, the central part is divided into upper and lower parts exactly in the middle, and more gadolinia is loaded than the lower part, or the position of the upper and lower divisions is near this (=j). However, it is not necessarily limited to this position.Also, another method is to increase the concentration at the top
Alternatively, a combination of enrichment difference and gadolinia difference can also be used.

また、上記各実施例では初装荷燃料について説明してい
るか、取替え燃料の場合には、すでに燃焼を経験した燃
料が炉心に装荷されており、これらの燃料では下部の燃
焼度がより進行しているために上部の濃縮度を高めたの
と同じ効果があるので、一般に初装荷燃料よりも出)J
ピーキングは小さい。したがって、取替え燃料では初装
荷燃料はとには上下に濃縮度差やガドリニア差をつCブ
る必要はなく、場合によっては中央部を2領域に分割し
なくてもよい。
In addition, in each of the above examples, the initial loading fuel is explained, or in the case of replacement fuel, fuel that has already experienced combustion is loaded into the reactor core, and with these fuels, the burnup in the lower part is more advanced. This has the same effect as increasing the enrichment at the top, so it generally produces more fuel than the initial load)J
Peaking is small. Therefore, in the case of replacement fuel, there is no need for the initially loaded fuel to have a difference in enrichment or gadolinia between the upper and lower sides, and in some cases, it is not necessary to divide the central portion into two regions.

第3図(a)ないしくd)は本発明の第3ないし第6の
実施例の燃料の軸方向の濃縮度・ガドリニア分イli図
て市る。なd3、これら各図にa5いて、横軸(j1濃
縮度を、縦軸は炉心高さを表しており、カドリニア装荷
量を少なくあるいは全く装荷しない部分を斜線で示して
おる。
FIGS. 3(a) to 3d) illustrate the axial enrichment and gadolinia content of the fuel in the third to sixth embodiments of the present invention. d3, a5 in each of these figures, the horizontal axis (j1) represents the enrichment, the vertical axis represents the core height, and the portions where the amount of quadrinia loaded is small or not loaded at all are shown with diagonal lines.

第3図(a)では上端部だりか、また第3図(b)では
下端部だ(プか低濃縮度になっており、各端部とそれに
隣接する部分だ【ブのガドリニア装荷量を少ナクシてい
る。第3図(C)cf5よび同図(d)では下端部およ
び下端部の両方が低濃縮度になっているが、カドリニア
装荷量か少ないのは両端部と何れか一方の隣接部だ(プ
である。
Figure 3(a) shows the upper end, and Figure 3(b) shows the lower end. In Fig. 3 (C) cf5 and Fig. 3 (d), both the lower end and the lower end have low enrichment, but the amount of cadrinia loaded is low at either end or at either end. It's the adjacent part.

上記各実施例では、第1および第2の実施例に比へると
その効果は小さくなるか、燃料経済性の改善効果が得ら
れることには変りない。また、これら第3・〜第6の各
実施例に、第1および第2実施例のような濃縮度や刀ト
リニア装荷量の分イIをもたせることもてきる。
In each of the above-mentioned embodiments, the effect becomes smaller when compared to the first and second embodiments, or the effect of improving fuel economy is still obtained. Further, each of the third to sixth embodiments can be provided with the same degree of enrichment and trilinear loading as the first and second embodiments.

[発明の効果] 以」]説明したように、本発明によれば、燃料の」ニ下
喘からの中性子の漏れの低減、ガドリニア残留量の低減
および出力の中央部分への集中によって、燃料集合体の
燃料経済性を著しく向上することができる。
[Effects of the Invention] As explained hereinafter, according to the present invention, by reducing the leakage of neutrons from the lower part of the fuel, reducing the residual amount of gadolinia, and concentrating the output in the central part, the fuel assembly can be improved. can significantly improve the body's fuel economy.

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

第1図は本発明の第1の実施例の燃Hの軸方向の濃縮度
・ガドリニア9411図、第2図は本発明の第2実施例
の燃料の軸方向の濃縮度・カドリニア分布図、第3図(
a)乃至同図(d)は本発明の第3実施例乃至第6実施
例の燃料の軸方向の濃縮度・ガドリニア分布図、第1図
d3よび第5図は従来の燃Hの軸方向の濃縮度・ノjト
リニア分411図、第6図は本発明と従来例にお(プる
炉心高さ方向のノットリニア残留量を比較した図、第7
図は本発明と従来例の炉心高さ方向の燃焼度を比較した
図、第8図は本発明と従来例の炉心高さ方向の相対用)
jを比較した図で市る。 (8733)代理人弁理士 猪股祥W (ばか1名)上
 鴻 下1も 第1図 第2図 第 3図 1坪 下婢 第4図 1帖 下方動 第5図 翅智晩戻 第7図 利均伝力 第8図
FIG. 1 is an axial enrichment/gadolinia 9411 diagram of fuel H according to the first embodiment of the present invention, and FIG. 2 is an axial enrichment/cadrinia distribution diagram of fuel H according to the second embodiment of the present invention. Figure 3 (
a) to (d) are axial enrichment/gadolinia distribution diagrams of the fuel of the third to sixth embodiments of the present invention, and Fig. 1 d3 to Fig. 5 are axial direction diagrams of the conventional fuel H. Figure 6 is a diagram comparing the not-linear residual amount in the core height direction between the present invention and the conventional example.
The figure is a comparison of the burnup in the core height direction of the present invention and the conventional example, and Figure 8 is a comparison of the burnup in the core height direction of the present invention and the conventional example)
Illustrated in a diagram comparing j. (8733) Representative Patent Attorney W. Inomata (1 idiot) 1. Figure 1. Figure 2. Figure 3. Uniform force diagram 8

Claims (1)

【特許請求の範囲】[Claims] 複数本の燃料棒を格子状に配列して構成される原子炉用
燃料集合体において、燃料集合体の上端部あるいは下端
部の少なくとも一方の核分裂物質含有量が当該燃料集合
体の他の部分の核分裂物質含有量よりも少なく、しかも
、前記核分裂物質含有量の少ない上端部あるいは下端部
およびこれらのうち少なくとも一方に隣接する部分の可
燃性毒物含有量が他の部分よりも小さいかまたはこれら
の部分には装荷されていないことを特徴とする原子炉用
燃料集合体。
In a nuclear reactor fuel assembly constructed by arranging a plurality of fuel rods in a lattice, the fissile material content of at least one of the upper end and lower end of the fuel assembly is higher than that of the other parts of the fuel assembly. The content of burnable poison is lower than the content of fissile material, and the burnable poison content of the upper end or the lower end and the parts adjacent to at least one of these parts is lower than the other parts, or these parts A fuel assembly for a nuclear reactor, characterized in that it is not loaded.
JP63132645A 1988-06-01 1988-06-01 Reactor fuel assemblies Expired - Lifetime JP2723252B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63132645A JP2723252B2 (en) 1988-06-01 1988-06-01 Reactor fuel assemblies

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63132645A JP2723252B2 (en) 1988-06-01 1988-06-01 Reactor fuel assemblies

Publications (2)

Publication Number Publication Date
JPH01304387A true JPH01304387A (en) 1989-12-07
JP2723252B2 JP2723252B2 (en) 1998-03-09

Family

ID=15086167

Family Applications (1)

Application Number Title Priority Date Filing Date
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Country Status (1)

Country Link
JP (1) JP2723252B2 (en)

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60117182A (en) * 1983-11-30 1985-06-24 株式会社東芝 Fuel aggregate for boiling-water type reactor
JPS61240193A (en) * 1985-04-17 1986-10-25 株式会社日立製作所 Fuel aggregate and nuclear reactor
JPS61260188A (en) * 1985-05-15 1986-11-18 株式会社東芝 Fuel aggregate
JPS63121789A (en) * 1986-11-12 1988-05-25 株式会社日立製作所 Nuclear reactor initial charging core

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60117182A (en) * 1983-11-30 1985-06-24 株式会社東芝 Fuel aggregate for boiling-water type reactor
JPS61240193A (en) * 1985-04-17 1986-10-25 株式会社日立製作所 Fuel aggregate and nuclear reactor
JPS61260188A (en) * 1985-05-15 1986-11-18 株式会社東芝 Fuel aggregate
JPS63121789A (en) * 1986-11-12 1988-05-25 株式会社日立製作所 Nuclear reactor initial charging core

Also Published As

Publication number Publication date
JP2723252B2 (en) 1998-03-09

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