JPH11174177A - Fuel assembly for boiling water reactor - Google Patents
Fuel assembly for boiling water reactorInfo
- Publication number
- JPH11174177A JPH11174177A JP9344677A JP34467797A JPH11174177A JP H11174177 A JPH11174177 A JP H11174177A JP 9344677 A JP9344677 A JP 9344677A JP 34467797 A JP34467797 A JP 34467797A JP H11174177 A JPH11174177 A JP H11174177A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- rod
- closest
- channel box
- light water
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【0001】[0001]
【発明の属する技術分野】本発明は、沸騰水型原子炉に
用いる燃料集合体に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fuel assembly used for a boiling water reactor.
【0002】[0002]
【従来の技術】原子炉の内部では核***反応により、ウ
ラン−235やプルトニウム−239などの核***性物
質の消耗とともに、ウラン−238やプルトニウム−2
40などの燃料親物質の核***性物質への変換が起って
いる。使用済燃料集合体取出時の核***性物質の生成率
と核***性物質の消費率の比を転換比と言う。ウラン資
源を有効に活用する方法として、転換比を高めることが
考えられている。転換比の向上は、原子炉内に装荷され
る燃料集合体内の水対燃料体積比を小さくすることによ
り中性子スペクトルを硬くし、ウラン−238やプルト
ニウム−240などの燃料親物質の中性子捕獲を促進す
ることにより実現できる。2. Description of the Related Art In a nuclear reactor, a nuclear fission reaction causes the depletion of fissile materials such as uranium-235 and plutonium-239, as well as uranium-238 and plutonium-2.
Conversion of fuel parent material, such as 40, to fissile material has occurred. The ratio between the rate of fissile material production and the rate of fissile material consumption during removal of spent fuel assemblies is called the conversion ratio. As a method of effectively utilizing uranium resources, increasing the conversion ratio is considered. Improvement of the conversion ratio makes the neutron spectrum hard by reducing the water-to-fuel volume ratio in the fuel assembly loaded in the reactor, and promotes neutron capture of fuel-parent substances such as uranium-238 and plutonium-240. This can be achieved by performing
【0003】燃料集合体内の水対燃料体積比を小さくす
ることによって転換比を向上する手段として、特開昭62
−64980 号公報あるいは特開昭61−275694号公報では、
矩形状のチャネルボックス内に、燃料棒を三角形格子状
に稠密配置する方法が示されている。As means for improving the conversion ratio by reducing the water-to-fuel volume ratio in the fuel assembly, Japanese Patent Application Laid-Open No.
-64980 or JP-A-61-275694,
A method is shown in which fuel rods are densely arranged in a triangular lattice in a rectangular channel box.
【0004】[0004]
【発明が解決しようとする課題】燃料集合体内の水対燃
料体積比を小さくする手段として考えられた、特開昭62
−64980 号公報あるいは特開昭61−275694号公報では、
矩形状のチャネルボックス内に三角形格子状に燃料棒配
列するため、チャネルボックスの4つの内側表面のうち
対向する2面は、他の2面と比較して燃料棒との間によ
り厚い軽水の層が存在する。そのため、この2面に面す
る燃料棒周辺の水対燃料体積比は、他の2面に面する燃
料棒周辺の水対燃料体積比より大きいくなっている。こ
うした水対燃料体積比の大きい領域では燃料棒の出力が
上昇し出力ピーキングが大きくなるという問題がある。SUMMARY OF THE INVENTION Japanese Unexamined Patent Publication No. Sho 62 (1987) was conceived as means for reducing the water to fuel volume ratio in a fuel assembly.
-64980 or JP-A-61-275694,
Since the fuel rods are arranged in a triangular grid in a rectangular channel box, two opposing surfaces of the four inner surfaces of the channel box have a thicker layer of light water between the fuel rods than the other two surfaces. Exists. Therefore, the water to fuel volume ratio around the fuel rods facing the two surfaces is larger than the water to fuel volume ratio around the fuel rods facing the other two surfaces. In such a region where the water to fuel volume ratio is large, there is a problem that the output of the fuel rod increases and the output peaking increases.
【0005】また、チャネルボックス内を流れる冷却材
が、稠密配置された燃料棒に流れにくく、水対燃料体積
比が大きい領域により多く流れるようになり、冷却能力
が低下するという問題がある。こうした出力ピーキング
の上昇と冷却能力の低下により燃料集合体の熱的余裕が
低下する。特開昭62−64980号公報あるいは特開昭61−2
75694号公報ではこれらの問題に何ら対策を取っていな
い。[0005] Further, there is a problem that the coolant flowing in the channel box hardly flows to the densely arranged fuel rods, and more coolant flows in a region where the water-to-fuel volume ratio is large, and the cooling capacity is reduced. Such an increase in output peaking and a decrease in cooling capacity decrease the thermal margin of the fuel assembly. JP-A-62-64980 or JP-A-61-264
No. 75694 does not take any measures against these problems.
【0006】本発明の目的は、チャネルボックス内側表
面に面する燃料棒の水対燃料体積比を小さくすることに
より、出力ピーキングを低減し、冷却材の流れの均一化
して冷却能力を向上し、燃料集合体の熱的余裕を向上す
ることにある。SUMMARY OF THE INVENTION It is an object of the present invention to reduce the output peaking by reducing the water-to-fuel volume ratio of the fuel rods facing the inner surface of the channel box, to improve the cooling capacity by making the coolant flow uniform, It is to improve the thermal margin of the fuel assembly.
【0007】[0007]
【課題を解決するための手段】上記目的を達成するため
に、本発明は図1に示すように、三角形の稠密格子に配
置した複数の燃料棒と、これらの燃料棒を囲む、断面形
状が四角筒状のチャネルボックスからなる燃料集合体に
おいて、前記チャネルボックスの4つの内側表面のう
ち、各面に最も近い前記燃料棒同士の間隙が他より広い
面と、この面に2番目に近い燃料棒との間の前記軽水が
存在する領域に、前記軽水より減速能の小さな物質を配
置したものである。To achieve the above object, the present invention, as shown in FIG. 1, comprises a plurality of fuel rods arranged in a triangular dense grid, and a cross-sectional shape surrounding these fuel rods. In a fuel assembly comprising a quadrangular cylindrical channel box, of the four inner surfaces of the channel box, a surface where the gap between the fuel rods closest to each surface is wider than the other, and a fuel second closest to this surface A substance having a smaller moderating power than the light water is arranged in an area where the light water exists between the rod and the rod.
【0008】本発明は、三角形の稠密格子に配置した複
数の燃料棒と、これらの燃料棒を囲む、断面形状が四角
筒状のチャネルボックスからなる燃料集合体において、
前記チャネルボックスの4つの内側表面のうち、各面に
最も近い前記燃料棒同士の間隙が他より広い面と、この
面に2番目に近い燃料棒との間の前記軽水が存在する領
域に、前記軽水より減速能の小さな物質が、前記チャネ
ルボックス内側表面の高さ全体にわたって配置してもよ
い。The present invention relates to a fuel assembly comprising a plurality of fuel rods arranged in a triangular dense grid and a channel box having a rectangular cross section and surrounding the fuel rods.
Of the four inner surfaces of the channel box, in a region where the light water exists between the surface where the gap between the fuel rods closest to each surface is larger than the other and the fuel rod second closest to this surface, A substance having a smaller moderating power than the light water may be disposed over the entire height of the inner surface of the channel box.
【0009】本発明は、三角形の稠密格子に配置した複
数の燃料棒と、これらの燃料棒を囲む、断面形状が四角
筒状のチャネルボックスからなる燃料集合体において、
前記チャネルボックスの4つの内側表面のうち、各面に
最も近い前記燃料棒同士の間隙が他より広い面と、この
面に2番目に近い燃料棒との間の前記軽水が存在する領
域に、前記軽水より減速能の小さな物質が、前記燃料棒
が存在する最も下の断面から少なくとも前記燃料棒の全
長の1/2の高さまで配置しても良い。According to the present invention, there is provided a fuel assembly comprising a plurality of fuel rods arranged in a triangular dense grid and a channel box having a rectangular cross section and surrounding the fuel rods.
Of the four inner surfaces of the channel box, in a region where the light water exists between the surface where the gap between the fuel rods closest to each surface is larger than the other and the fuel rod second closest to this surface, The substance having a smaller moderating power than the light water may be arranged at least from a lowermost section where the fuel rod is present to a height of a half of the entire length of the fuel rod.
【0010】[0010]
【発明の実施の形態】本発明の第1の実施例を図1に示
す。燃料集合体1は三角形の稠密格子に配置した燃料棒
5とそれを囲むチャネルボックス9からなる。チャネル
ボックス9内の燃料棒5が存在しない領域は軽水13で
満たされている。チャネルボックス9の内側表面、9
a,9b,9c,9dの中で、面9aと面9cに最も近
い燃料棒同士の間隙は、面9bと面9dに最も近い燃料
棒同士の間隙より広くなっている。この面9a,面9c
と各面に2番目に近い燃料棒との間の軽水13が存在す
る領域に、燃料棒5と同一の直径を持ち断面の形状が半
円形の水排除棒17を、面9a,面9cの高さ全体にわ
たって配置する。水排除棒17は軽水13を排除すると
いう目的を満たすのであれば、本実施例により断面形状
を限定されるものではない。FIG. 1 shows a first embodiment of the present invention. The fuel assembly 1 includes fuel rods 5 arranged in a triangular dense lattice and a channel box 9 surrounding the fuel rods. A region in the channel box 9 where the fuel rods 5 do not exist is filled with light water 13. Inner surface of channel box 9, 9
Among the fuel rods a, 9b, 9c, and 9d, the gap between the fuel rods closest to the face 9a and the face 9c is wider than the gap between the fuel rods closest to the face 9b and the face 9d. These surfaces 9a and 9c
In the region where the light water 13 exists between the fuel rods and the second closest fuel rod on each surface, a water exclusion rod 17 having the same diameter as that of the fuel rod 5 and a semicircular cross section is provided on the surfaces 9a and 9c. Place over the entire height. The cross-sectional shape of the water removal rod 17 is not limited by the present embodiment as long as the purpose of removing the light water 13 is satisfied.
【0011】本実施例の比較例として従来技術の沸騰水
型原子炉用燃料集合体を図2に示す。燃料集合体2は三
角形の稠密格子に配置した燃料棒6とそれを囲むチャネ
ルボックス10からなる。チャネルボックス10内の燃
料棒6が存在しない領域は軽水14で満たされている。
従来技術の燃料集合体2では、面10a,面10cと各
面に2番目に近い燃料棒の間に軽水14の厚い層が存在
するため、この燃料棒の周辺では水対燃料体積比が大き
い。そのため、これらの燃料棒の出力が高くなり、出力
ピーキングが大きい。また、冷却材としてチャネルボッ
クス10内を流れる軽水14は、水対燃料体積比が大き
いこれらの領域により多く流れ、稠密配置された燃料棒
6の周辺には流れにくくなる。FIG. 2 shows a conventional fuel assembly for a boiling water reactor as a comparative example of this embodiment. The fuel assembly 2 includes fuel rods 6 arranged in a triangular dense lattice and a channel box 10 surrounding the fuel rods. The area in the channel box 10 where the fuel rods 6 do not exist is filled with light water 14.
In the fuel assembly 2 of the prior art, since a thick layer of light water 14 exists between the surfaces 10a and 10c and the fuel rod closest to each surface, the water-to-fuel volume ratio is large around this fuel rod. . Therefore, the output of these fuel rods increases, and the output peaking is large. Further, the light water 14 flowing in the channel box 10 as a coolant flows more in these regions where the water-to-fuel volume ratio is large, and hardly flows around the densely arranged fuel rods 6.
【0012】本発明の第1の実施例では水排除棒17に
より面9aと面9cに最も近い燃料棒の周辺の水対燃料
体積比を、面9bと9dに最も近い燃料棒の周りの水対
燃料体積比と同等まで小さくすることができる。本実施
例により、面9aと面9cに最も近い燃料棒の出力を低
減することができ、出力ピーキングも低減できる。ま
た、冷却材としてチャネルボックス9内を流れる軽水1
3の流れを均一化できる。In the first embodiment of the present invention, the water drainage rod 17 is used to determine the water-to-fuel volume ratio around the fuel rod closest to the surfaces 9a and 9c and the water around the fuel rod closest to the surfaces 9b and 9d. It can be reduced to the same as the fuel volume ratio. According to this embodiment, the output of the fuel rod closest to the surfaces 9a and 9c can be reduced, and the output peaking can also be reduced. Light water 1 flowing through the channel box 9 as a coolant
3 can be made uniform.
【0013】本発明の第2の実施例を図3に示す。燃料
集合体3のA−A′の横断面図を図4に示す。燃料集合
体3は三角形の稠密格子に配置した燃料棒7とそれを囲
むチャネルボックス11からなる。チャネルボックス1
1内の燃料棒7が存在しない領域は軽水15で満たされ
ている。チャネルボックス11の内側表面、11a,1
1b,11c,11dの中で、面11aと面11cに最
も近い燃料棒同士の間隙は、面11bと面11dに最も
近い燃料棒同士の間隙より広くなっている。この面11
a,面11cと各面に2番目に近い燃料棒との間の軽水
15が存在する領域に、燃料棒7と同一の直径を持ち断
面の形状が半円形の水排除棒18を、燃料棒7が存在す
る下端の断面から燃料棒7の1/2の高さまで配置す
る。FIG. 3 shows a second embodiment of the present invention. FIG. 4 shows a cross-sectional view taken along the line AA ′ of the fuel assembly 3. The fuel assembly 3 includes fuel rods 7 arranged in a triangular dense lattice and a channel box 11 surrounding the fuel rods 7. Channel box 1
1 is filled with light water 15 in a region where the fuel rods 7 do not exist. Inner surface of channel box 11, 11a, 1
Among 1b, 11c, and 11d, the gap between the fuel rods closest to the surfaces 11a and 11c is wider than the gap between the fuel rods closest to the surfaces 11b and 11d. This face 11
a, in a region where the light water 15 exists between the surface 11c and the fuel rod second closest to each surface, a water exclusion rod 18 having the same diameter as the fuel rod 7 and having a semicircular cross section, The fuel rods 7 are arranged from the cross section at the lower end where the fuel rods 7 exist to half the height of the fuel rod 7.
【0014】沸騰水型原子炉では燃料集合体下部領域は
ボイド率が小さいため、燃料集合体上部領域より水対燃
料体積比が大きい。従って、水排除棒による水対燃料体
積比の低減効果は、燃料集合体下部領域の方が燃料集合
体上部領域より大きい。この燃料集合体下部領域に水排
除棒18を配置することにより効果的に水対燃料体積比
を小さくするとともに、第1の実施例と比較して、水排
除棒18を短くすることにより、燃料集合体上部領域の
圧力損失を低減することができる。In the boiling water reactor, since the lower area of the fuel assembly has a smaller void fraction, the water to fuel volume ratio is larger than that of the upper area of the fuel assembly. Therefore, the effect of reducing the water to fuel volume ratio by the water exclusion rod is greater in the lower region of the fuel assembly than in the upper region of the fuel assembly. By arranging the water exclusion rod 18 in the lower region of the fuel assembly, the water-to-fuel volume ratio can be effectively reduced, and by shortening the water exclusion rod 18 compared with the first embodiment, the fuel can be reduced. The pressure loss in the upper region of the assembly can be reduced.
【0015】本発明の第3の実施例を図5に示す。燃料
集合体4は三角形の稠密格子に配置した燃料棒8とそれ
を囲むチャネルボックス12からなる。チャネルボック
ス12内の燃料棒8が存在しない領域は軽水16で満た
されている。チャネルボックス12の内側表面、12
a,12b,12c,12dの中で、面12aと面12
cに最も近い燃料棒同士の間隙は、面12bと面12d
に最も近い燃料棒同士の間隙より広くなっている。この
面12a,面12cと各面に2番目に近い燃料棒との間
の軽水16が存在する領域に、燃料棒8と同一の直径を
持ち内部に炭素を充填した断面の形状が半円形の水排除
棒19を、燃料棒8が存在するすべての断面において配
置する。本実施例によれば水排除棒19内に軽水より減
速能の小さい炭素を充填することにより、面12aと面
12cに最も近い燃料棒の周辺の水対燃料体積比を小さ
くすることがきできる。FIG. 5 shows a third embodiment of the present invention. The fuel assembly 4 includes fuel rods 8 arranged in a triangular dense lattice and a channel box 12 surrounding the fuel rods 8. The area in the channel box 12 where the fuel rods 8 do not exist is filled with light water 16. Inner surface of channel box 12, 12
a, 12b, 12c and 12d, the surface 12a and the surface 12a
The gap between the fuel rods closest to c is equal to the surface 12b and the surface 12d.
It is wider than the gap between the fuel rods closest to. In the region where the light water 16 exists between the surfaces 12a and 12c and the fuel rod closest to each surface, the cross-sectional shape of the fuel rod 8 having the same diameter and filled with carbon is semicircular. The water exclusion rods 19 are arranged in all sections where the fuel rods 8 are present. According to this embodiment, the water-to-fuel volume ratio around the fuel rod closest to the surface 12a and the surface 12c can be reduced by filling the water exclusion rod 19 with carbon having smaller deceleration ability than light water.
【0016】[0016]
【発明の効果】本発明によれば、沸騰水型原子炉におい
て、水対燃料体積比を小さくすることにより、出力ピー
キングを低減および冷却材の流れの均一化を実現した燃
料集合体を提供することができる。According to the present invention, in a boiling water reactor, there is provided a fuel assembly which realizes a reduction in power peaking and a uniform flow of coolant by reducing the water to fuel volume ratio. be able to.
【図1】本発明の第1の実施例の燃料集合体を示す横断
面図。FIG. 1 is a cross-sectional view showing a fuel assembly according to a first embodiment of the present invention.
【図2】本発明の第1の実施例に対する比較例の従来型
の沸騰水型原子炉用の燃料集合体を示す横断面図。FIG. 2 is a cross-sectional view showing a fuel assembly for a conventional boiling water reactor as a comparative example with respect to the first embodiment of the present invention.
【図3】本発明の第2の実施例の燃料集合体を示す縦断
面図。FIG. 3 is a longitudinal sectional view showing a fuel assembly according to a second embodiment of the present invention.
【図4】図3のA−A線断面図。FIG. 4 is a sectional view taken along line AA of FIG. 3;
【図5】本発明の第3の実施例の燃料集合体を示す横断
面図。FIG. 5 is a cross-sectional view showing a fuel assembly according to a third embodiment of the present invention.
1,2,3,4…燃料集合体、5,6,7,8…燃料
棒、9,10,11,12…チャネルボックス、9a,
9b,9c,9d…チャネルボックス9の内側表面、1
0a,10b,10c,10d…チャネルボックス10
の内側表面、11a,11b,11c,11d…チャネ
ルボックス11の内側表面、12a,12b,12c,
12d…チャネルボックス12の内側表面、13,1
4,15,16…軽水、17,18,19…水排除棒。1, 2, 3, 4 ... fuel assembly, 5, 6, 7, 8 ... fuel rod, 9, 10, 11, 12 ... channel box, 9a,
9b, 9c, 9d ... inner surface of channel box 9, 1
0a, 10b, 10c, 10d ... channel box 10
, 11a, 11b, 11c, 11d... Inside surface of the channel box 11, 12a, 12b, 12c,
12d: Inside surface of the channel box 12, 13, 1
4, 15, 16 ... light water, 17, 18, 19 ... water removal rod.
Claims (4)
子炉の炉心部に装荷され、核***性物質を含む燃料物質
を内包し、三角形の稠密格子に配置した複数の燃料棒
と、これらの燃料棒を囲む、断面形状が四角筒状のチャ
ネルボックスからなる燃料集合体において、前記チャネ
ルボックスの4つの内側表面のうち、各面に最も近い前
記燃料棒同士の間隙が他より広い面と、この面に2番目
に近い燃料棒との間の前記軽水が存在する領域に、前記
軽水より減速能の小さな物質が存在することを特徴とす
る沸騰水型原子炉用燃料集合体。1. A plurality of fuel rods which are loaded in a core of a nuclear reactor using light water as a coolant and a moderator, contain a fuel material containing a fissile material, and are arranged in a triangular dense lattice. In a fuel assembly including a rod-shaped channel box having a cross-sectional shape of a quadrangular cylinder, a surface of the four inner surfaces of the channel box, in which a gap between the fuel rods closest to each surface is wider than the other surface, A fuel assembly for a boiling water reactor, wherein a substance having a smaller moderating power than that of the light water is present in a region where the light water exists between the fuel rod and a fuel rod closest to a surface.
子炉の炉心部に装荷され、核***性物質を含む燃料物質
を内包し、三角形の稠密格子に配置した複数の燃料棒
と、これらの燃料棒を囲む、断面形状が四角筒状のチャ
ネルボックスからなる燃料集合体において、前記チャネ
ルボックスの4つの内側表面のうち、各面に最も近い前
記燃料棒同士の間隙が他より広い面と、この面に2番目
に近い燃料棒との間の前記軽水が存在する領域に、前記
軽水より減速能の小さな物質が、前記チャネルボックス
内側表面の高さ全体にわたって存在することを特徴とす
る沸騰水型原子炉用燃料集合体。2. A plurality of fuel rods which are loaded in a core of a nuclear reactor using light water as a coolant and a moderator, contain a fuel material containing a fissile material, and are arranged in a triangular dense lattice. In a fuel assembly including a rod-shaped channel box having a cross-sectional shape of a quadrangular cylinder, a surface of the four inner surfaces of the channel box, in which a gap between the fuel rods closest to each surface is wider than the other surface, A boiling water type in which a substance having a moderating power smaller than that of the light water is present over the entire height of the inner surface of the channel box in a region where the light water exists between the fuel rod and a fuel rod closest to the surface. Reactor fuel assemblies.
子炉の炉心部に装荷され、核***性物質を含む燃料物質
を内包し、三角形の稠密格子に配置した複数の燃料棒
と、これらの燃料棒を囲む、断面形状が四角筒状のチャ
ネルボックスからなる燃料集合体において、前記チャネ
ルボックスの4つの内側表面のうち、各面に最も近い前
記燃料棒同士の間隙が他より広い面と、この面に2番目
に近い燃料棒との間の前記軽水が存在する領域に、前記
軽水より減速能の小さな物質が、前記燃料棒が存在する
最も下の断面から少なくとも前記燃料棒の全長の1/2
の高さまで存在することを特徴とする沸騰水型原子炉用
燃料集合体。3. A plurality of fuel rods which are loaded in a core of a nuclear reactor using light water as a coolant and a moderator, contain a fuel material containing a fissile material, and are arranged in a triangular dense lattice. In a fuel assembly including a rod-shaped channel box having a cross-sectional shape of a quadrangular cylinder, a surface of the four inner surfaces of the channel box, in which a gap between the fuel rods closest to each surface is wider than the other surface, In a region where the light water exists between the fuel rod and the second closest fuel rod to the surface, a substance having a smaller moderating power than the light water has at least one-half of the entire length of the fuel rod from the lowest cross section where the fuel rod is present. 2
A fuel assembly for a boiling water reactor, wherein the fuel assembly is present up to the height of.
少なくとも1体以上に、前記核***性物質としてウラン
・プルトニウム混合酸化物燃料を含むことを特徴とする
沸騰水型原子炉用燃料集合体。4. A fuel for a boiling water reactor according to claim 1, wherein at least one of said fuel rods contains a uranium-plutonium mixed oxide fuel as said fissile material. Aggregation.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP9344677A JPH11174177A (en) | 1997-12-15 | 1997-12-15 | Fuel assembly for boiling water reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP9344677A JPH11174177A (en) | 1997-12-15 | 1997-12-15 | Fuel assembly for boiling water reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH11174177A true JPH11174177A (en) | 1999-07-02 |
Family
ID=18371131
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP9344677A Pending JPH11174177A (en) | 1997-12-15 | 1997-12-15 | Fuel assembly for boiling water reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH11174177A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US7027122B2 (en) | 2002-03-12 | 2006-04-11 | Lg.Philips Lcd Co., Ltd. | Bonding apparatus having compensating system for liquid crystal display device and method for manufacturing the same |
JP2021162406A (en) * | 2020-03-31 | 2021-10-11 | 日立Geニュークリア・エナジー株式会社 | Boiling water reactor |
-
1997
- 1997-12-15 JP JP9344677A patent/JPH11174177A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US7027122B2 (en) | 2002-03-12 | 2006-04-11 | Lg.Philips Lcd Co., Ltd. | Bonding apparatus having compensating system for liquid crystal display device and method for manufacturing the same |
JP2021162406A (en) * | 2020-03-31 | 2021-10-11 | 日立Geニュークリア・エナジー株式会社 | Boiling water reactor |
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