JPS6260039B2 - - Google Patents
Info
- Publication number
- JPS6260039B2 JPS6260039B2 JP56119118A JP11911881A JPS6260039B2 JP S6260039 B2 JPS6260039 B2 JP S6260039B2 JP 56119118 A JP56119118 A JP 56119118A JP 11911881 A JP11911881 A JP 11911881A JP S6260039 B2 JPS6260039 B2 JP S6260039B2
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- rod guide
- guide thimble
- support
- fuel assembly
- 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
Links
- 239000000446 fuel Substances 0.000 claims description 44
- 239000003758 nuclear fuel Substances 0.000 claims description 16
- 238000010168 coupling process Methods 0.000 claims description 3
- 230000008878 coupling Effects 0.000 claims description 2
- 238000005859 coupling reaction Methods 0.000 claims description 2
- 238000010586 diagram Methods 0.000 description 4
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 238000005452 bending Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 238000006073 displacement reaction Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 238000005219 brazing Methods 0.000 description 1
- 230000001934 delay Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 238000010297 mechanical methods and process Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
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)
- Fuel-Injection Apparatus (AREA)
Description
【発明の詳細な説明】
この発明は原子燃料集合体の改良に関するもの
である。DETAILED DESCRIPTION OF THE INVENTION This invention relates to improvements in nuclear fuel assemblies.
加圧水型原子炉の燃料集合体はその骨格を、支
持格子と制御棒案内シンブルもしくはインサート
と呼ばれるシース（以下制御棒案内シンブルとい
う）を剛結合して形成したのち、燃料棒を支持格
子のセルに挿入し、最後に制御棒案内シンブルの
端部に上部および下部ノズルを固着し組立られ
る。 The skeleton of a fuel assembly for a pressurized water reactor is formed by rigidly connecting a support grid and a sheath called a control rod guide thimble or insert (hereinafter referred to as a control rod guide thimble), and then the fuel rods are inserted into the cells of the support grid. The control rod guide thimble is then inserted and finally assembled by securing the upper and lower nozzles to the ends of the control rod guide thimble.
このような構造の燃料集合体を原子炉内で使用
した場合、中性子照射による成長、熱膨張等によ
る燃料棒の軸方向の伸びが非一様であること等に
基因する曲げモーメントが支持格子を経由して骨
格に直接作用し、燃料集合体の変形（典型的には
軸方向弓なり）を惹起する結果となる。燃料集合
体が変形すると、燃料集合体の炉心からの取り出
しあるいは炉心への装荷作業が著しく困難にな
り、作業時間の遅延のみならず燃料集合体の無理
な装荷取出しにより燃料集合体が損傷するなどの
問題があつた。 When a fuel assembly with such a structure is used in a nuclear reactor, the bending moment due to non-uniform growth in the axial direction of the fuel rods due to growth due to neutron irradiation, thermal expansion, etc. It acts directly on the skeleton via the fuel assembly, resulting in deformation (typically axial bowing) of the fuel assembly. If the fuel assembly is deformed, it becomes extremely difficult to remove the fuel assembly from the core or load it into the reactor core, which not only delays the work time but also causes damage to the fuel assembly due to forced loading and unloading of the fuel assembly. There was a problem.
この発明は上記の如き事情に鑑みてなされたも
のであつて、燃料棒に軸方向非一様の伸びが生じ
ても燃料集合体の変形を容易に低減し得る原子燃
料集合体を提供することを目的とするものであ
る。 The present invention has been made in view of the above circumstances, and an object of the present invention is to provide a nuclear fuel assembly that can easily reduce deformation of the fuel assembly even if non-uniform elongation occurs in the axial direction of the fuel rods. The purpose is to
この目的に対応して、この発明の原子燃料集合
体は、複数本の制御棒案内シンブルの上端に上部
ノズル、下端に下部ノズルがそれぞれ固着され、
制御棒案内シンブルの軸方向に複数個の支持格子
が隔置され、かつ、支持格子の格子セルに燃料棒
が挿通される原子燃料集合体において、支持格子
の制御棒案内シンブルを挿通させる格子セルは格
子帯板の巾より長いカラーを備え、カラー内に挿
通した制御棒案内シンブルとカラーとの係合を、
最上段支持格子および最下段支持格子においては
機械的結合あるいは冶金的接合による剛結合と
し、最上段および最下段支持格子を除く他の支持
格子の一若しくは二以上においては、挿通した制
御棒案内シンブルの軸方向にカラーの長さより大
きな間隔で二つの突起を形成し、二つの突起間に
支持格子を軸方向に摺動可能に受け入れたことを
特徴としている。 Corresponding to this purpose, the nuclear fuel assembly of the present invention has an upper nozzle fixed to the upper end of a plurality of control rod guide thimbles, and a lower nozzle fixed to the lower end thereof,
In a nuclear fuel assembly in which a plurality of support grids are spaced apart in the axial direction of the control rod guide thimble and fuel rods are inserted into the grid cells of the support grid, a grid cell into which the control rod guide thimble of the support grid is inserted. is equipped with a collar that is longer than the width of the lattice strip, and the engagement between the control rod guide thimble inserted into the collar and the collar is
The uppermost support grid and the lowermost support grid are rigidly connected by mechanical or metallurgical bonding, and one or more of the other support grids other than the uppermost and lowest support grids have control rod guide thimble inserted through them. Two protrusions are formed at a distance greater than the length of the collar in the axial direction, and a support grid is slidably received in the axial direction between the two protrusions.
以下この発明の詳細を一実施例を示す図面につ
いて説明する。 The details of this invention will be explained below with reference to the drawings showing one embodiment.
第１図及び第２図において１００は原子燃料集
合体であり、原子燃料集合体１００は複数の制御
棒案内シンブル１の軸方向に複数個の支持格子２
が隔置された関係で結合されており、前記支持格
子２は制御棒案内シンブルが挿通されるセル４′
のほか燃料棒５が挿通される多数のセル４を有し
ている。燃料集合体１００の組立は複数本の制御
棒案内シンブル１に複数個の支持格子２を剛結合
および摺動可能に嵌合して骨格３を形成したの
ち、格子セル４に燃料棒５を挿通し、最後に上部
ノズル６および下部ノズル７を前記制御棒案内シ
ンブル１の端部に公知の手段により冶金的あるい
は機械的に固着結合する。（第１図、第２図で
は、骨格３を明確にするため、燃料棒５は２本の
み示し他は省略してある。）
第３図は制御棒案内シンブル１と支持格子２の
間の剛結合構造を示すもので、支持格子２の制御
棒案内シンブル挿通セル４′には格子帯板の巾Ｗ
より長い円筒状のカラー８がろう付等の方法によ
り固着される。制御棒案内シンブル１は前記カラ
ー８内に挿通され前記支持格子２を軸方向の所定
位置に位置決めしたのち前記制御棒案内シンブル
１の内側から拡管冶具を用いて膨出加工を施し拡
管部９を形成することにより支持格子と制御棒案
内シンブルを剛結合する。この剛結合方式は従来
公知の加圧水型原子燃料集合体において全ての支
持格子の結合に採用されていたもので、この発明
の原子燃料集合体１００においては少なくとも最
上段支持格子２ａと最下段支持格子２ｂに適用す
る。 1 and 2, 100 is a nuclear fuel assembly, and the nuclear fuel assembly 100 includes a plurality of support grids 2 in the axial direction of a plurality of control rod guide thimble 1.
are coupled in spaced relation, said support grid 2 having cells 4' through which control rod guide thimbles are inserted.
In addition, it has a large number of cells 4 into which fuel rods 5 are inserted. The fuel assembly 100 is assembled by rigidly connecting and slidably fitting a plurality of support grids 2 to a plurality of control rod guide thimble 1 to form a skeleton 3, and then inserting fuel rods 5 into the grid cells 4. Finally, the upper nozzle 6 and the lower nozzle 7 are fixedly connected to the ends of the control rod guide thimble 1 by metallurgical or mechanical methods known in the art. (In Figures 1 and 2, in order to clarify the skeleton 3, only two fuel rods 5 are shown and the others are omitted.) Figure 3 shows the structure between the control rod guide thimble 1 and the support grid 2. This shows a rigid connection structure, and the control rod guide thimble insertion cell 4' of the support grid 2 has the width W of the grid strip.
A longer cylindrical collar 8 is fixed by a method such as brazing. After the control rod guide thimble 1 is inserted into the collar 8 and the support grid 2 is positioned at a predetermined position in the axial direction, the control rod guide thimble 1 is bulged from the inside using a tube expansion jig to form the tube expansion part 9. This rigidly connects the support grid and the control rod guide thimble. This rigid coupling method has been adopted for coupling all support grids in conventionally known pressurized water type nuclear fuel assemblies, and in the nuclear fuel assembly 100 of the present invention, at least the uppermost support grid 2a and the lowermost support grid Applies to 2b.
前記複数の支持格子のうち、最上段および最下
段支持格子２ａ，２ｂを除く他の支持格子２ｃ，
２ｄ……と制御棒案内シンブルとの係合構造は第
４図に示すように支持格子２に固着されたカラー
８内に制御棒案内シンブル１を挿通したのち前記
カラー８の長さＬより大きな間隔を以つて前記制
御棒案内シンブルに突起１０および１０′を形成
する。突起１０，１０′の形成は膨出冶具による
拡管加工でもよいし、あるいは第３図に示すよう
に制御棒案内シンブル１の外側に筒状のストツパ
ー１１および１１′を溶接あるいはネヅ嵌めして
もよい。 Among the plurality of support grids, other support grids 2c, excluding the uppermost and lowermost support grids 2a and 2b,
2d... and the control rod guide thimble, as shown in FIG. 4, after inserting the control rod guide thimble 1 into the collar 8 fixed to the support grid 2, Projections 10 and 10' are formed on the control rod guide thimble at intervals. The protrusions 10, 10' may be formed by expanding the tubes using a bulging jig, or by welding or threading cylindrical stoppers 11 and 11' on the outside of the control rod guide thimble 1, as shown in FIG. Good too.
このように構成した原子燃料集合体１００にお
いては、最上段支持格子２ａおよび最下段支持格
子２ｂは制御棒案内シンブル１に剛結合されてお
り、多数の支持格子セル４に挿通された燃料棒５
の全重量および燃料棒５に生起する力は前記支持
格子を経由して前記剛結合部から制御棒案内シン
ブル１へと伝わる。一方、前記最上段および最下
段支持格子２ａ，２ｂを除く他の７個の支持格子
２ｃ，２ｄ……は各格子セル４内において燃料棒
５を弾性支持し、冷却材チヤンネルを維持する効
果をもつという点では前記剛結合した最上段およ
び最下段支持格子２ａ，２ｂと同様であるが、制
御棒案内シンブル１との嵌合部が第４図、第５図
に示した様に摺動可能な構造のため燃料棒５に生
起する軸力を制御棒案内シンブル１に伝達するこ
とがない。また、前記支持格子が原子炉内を下か
ら上に向かつて流れる冷却材により押し上げられ
ようとしたり、あるいは、支持格子自身の重量等
によりずり落ちようとすると制御棒案内シンブル
に設けた突起１０，１０′が支持格子のカラー８
に当つて、軸方向の変位を限定した範囲内に止め
る。 In the nuclear fuel assembly 100 configured as described above, the uppermost support grid 2a and the lowermost support grid 2b are rigidly connected to the control rod guide thimble 1, and the fuel rods 5 inserted through the numerous support grid cells 4 are connected rigidly to the control rod guide thimble 1.
The entire weight of the fuel rods 5 and the forces occurring on the fuel rods 5 are transmitted from the rigid connections to the control rod guide thimble 1 via the support grid. On the other hand, the other seven support grids 2c, 2d, excluding the uppermost and lowermost support grids 2a, 2b, elastically support the fuel rods 5 in each grid cell 4, and have the effect of maintaining the coolant channel. It is similar to the rigidly connected uppermost and lowermost support grids 2a and 2b in that it has a structure, but the fitting part with the control rod guide thimble 1 is slidable as shown in FIGS. 4 and 5. Because of this structure, the axial force generated in the fuel rods 5 is not transmitted to the control rod guide thimble 1. In addition, if the support grid tries to be pushed up by the coolant flowing from bottom to top inside the reactor, or if it tries to slide down due to its own weight, the protrusion 10 provided on the control rod guide thimble, 10' is the support grid collar 8
In doing so, the displacement in the axial direction is kept within a limited range.
第６図および第７図は、構造強度解析結果を示
すもので、第６図は制御棒案内シンブルに剛結合
する支持格子数と集合体変形量の関係を示し、第
７図は剛結合した支持格子数と支持格子１個に作
用する荷重の関係を示している。 Figures 6 and 7 show the results of structural strength analysis. Figure 6 shows the relationship between the number of support grids rigidly connected to the control rod guide thimble and the deformation of the aggregate, and Figure 7 shows the relationship between the number of support grids rigidly connected to the control rod guide thimble and the amount of deformation of the aggregate. It shows the relationship between the number of support grids and the load acting on one support grid.
これら第６図、第７図から明らかなように、原
子燃料集合体において制御棒案内シンブル１に剛
結合される支持格子数が増すにつれ集合体変形量
が大となり、支持格子１個あたりに働く荷重は逆
に小さくなる。 As is clear from these Figures 6 and 7, as the number of support grids rigidly connected to the control rod guide thimble 1 in a nuclear fuel assembly increases, the amount of deformation of the assembly increases, and the amount of deformation applied to each support grid increases. On the contrary, the load becomes smaller.
したがつて、燃料棒軸力のアンバランスによつ
て生じる曲げモーメントが制御棒案内シンブルに
作用しないようにするには、制御棒案内シンブル
に剛結合する支持格子数を少くすればする程効果
的なことが明らかであるが、すべての支持格子に
ついて制御棒案内シンブルとの剛結合を解くと、
燃料棒の重量を支えることができずに支持格子２
は燃料棒５と共に燃料棒下端が下部ノズル７に座
着するまでずり落ちてしまい、また、構造的にも
不安定になる。好ましい一例としての原子燃料集
合体においては、前記解析結果に基づき最適条件
として最上段および最下段支持格子を剛結合と
し、他の支持格子を摺動可能としたものである。 Therefore, in order to prevent the bending moment caused by the unbalance of the fuel rod axial force from acting on the control rod guide thimble, it is more effective to reduce the number of support grids that are rigidly connected to the control rod guide thimble. It is clear that, when the rigid connections with the control rod guide thimble are removed for all support grids,
The support grid 2 cannot support the weight of the fuel rods.
The lower ends of the fuel rods will slide down together with the fuel rods 5 until they are seated in the lower nozzles 7, and the structure will also become unstable. In a nuclear fuel assembly as a preferred example, the uppermost and lowermost support grids are rigidly connected as an optimum condition based on the above analysis results, and the other support grids are made slidable.
また、更に構造的に万全を期すならば、最上段
支持格子２ａとその直下の支持格子２ｃおよび最
下段支持格子２ｂの３個を制御棒案内シンブルと
剛結合することにより構造的に安定で、かつ、燃
料集合体変形にも効果があることが解析の結果明
らかとなつた。尚、前記のものは９個の支持格子
を持つ燃料集合体の解析結果であるが、他のタイ
プ（例えば７グリツドの燃料集合体）についても
同様の結果が得られた。 Furthermore, to ensure structural integrity, the top support grid 2a, the support grid 2c immediately below it, and the bottom support grid 2b can be rigidly connected to the control rod guide thimble to ensure structural stability. Moreover, the analysis results revealed that it is also effective in deforming fuel assemblies. Although the above is an analysis result of a fuel assembly having nine support grids, similar results were obtained for other types (for example, a fuel assembly with seven grids).
以上は通常運転時の燃料の健全性を重視した構
造例であるが、地震時には燃料集合体は軸方向中
央部支持格子を最大変位とする弓形の振動をし、
その場合当該支持格子には、衝突に伴う地震衝撃
力が加わるので、地震力が大きい場合にはその配
慮が必要となる場合もある。すなわち、大きい地
震力に対しても燃料集合体の健全性を維持するに
は、集合体軸方向中央部およびその近傍の支持格
子を制御棒案内シンブルと剛結合し、燃料集合体
の構造強度を補強するのが望ましいことが耐震解
析の結果わかつた。したがつて、前述のような場
合にあつては、燃料集合体の耐震性能を補強する
ため、集合体軸方向中央部の支持格子のいくつか
（2f等）を制御棒案内シンブルと剛結合すること
が好ましい。 The above is an example of a structure that emphasizes the soundness of the fuel during normal operation, but in the event of an earthquake, the fuel assembly vibrates in an arcuate manner with the maximum displacement at the central support grid in the axial direction.
In this case, the support grid is subject to earthquake impact force due to the collision, so consideration may be required if the earthquake force is large. In other words, in order to maintain the integrity of the fuel assembly even in the face of large seismic forces, the support grid at and near the axial center of the assembly is rigidly connected to the control rod guide thimble to increase the structural strength of the fuel assembly. As a result of seismic analysis, it was found that it is desirable to strengthen the building. Therefore, in the case described above, some of the support grids (such as 2f) in the axial center of the fuel assembly should be rigidly connected to the control rod guide thimble in order to reinforce the seismic performance of the fuel assembly. It is preferable.
以上説明したように、この発明の原子燃料集合
体は制御棒案内シンブルに剛結合する支持格子数
を必要量少限かつ最適に配置し、更に、軸方向摺
動可能な支持格子を設けたので、燃料棒に生起す
る軸方向非一様の伸びを吸収し、燃料集合体の変
形を容易に低減することができる。 As explained above, in the nuclear fuel assembly of the present invention, the number of support grids that are rigidly connected to the control rod guide thimble is minimized and optimally arranged, and furthermore, the support grid that is slidable in the axial direction is provided. , it is possible to absorb non-uniform elongation of the fuel rods in the axial direction and easily reduce deformation of the fuel assembly.
また摺動可能な支持格子の制御棒案内シンブル
嵌合部以外は従来の燃料集合体構造と全く同一で
あるため設計変更も極めて容易で、かつ、加工も
簡便である。 In addition, since the structure of the fuel assembly is exactly the same as that of the conventional fuel assembly except for the control rod guide thimble fitting portion of the slidable support grid, design changes are extremely easy and processing is also simple.
第１図は本発明の燃料集合体構造図、第２図は
第１図におけるＡ−Ａ部断面拡大図、第３図は支
持格子剛結合構造概略図、第４図は支持格子摺動
構造概略図、第５図は摺動構造の他の実施例を示
す図、第６図および第７図は構造強度解析結果を
示すグラフである。
１……制御棒案内シンブル、２……支持格子、
３……骨格、４……セル、５……燃料棒、８……
カラー、９……拡管部、１０，１０′……突起、
１１，１１′……ストツパー。
Fig. 1 is a structural diagram of a fuel assembly according to the present invention, Fig. 2 is an enlarged cross-sectional view of section A-A in Fig. 1, Fig. 3 is a schematic diagram of a support grid rigid connection structure, and Fig. 4 is a support grid sliding structure. A schematic diagram, FIG. 5 is a diagram showing another example of the sliding structure, and FIGS. 6 and 7 are graphs showing the results of structural strength analysis. 1...Control rod guide thimble, 2...Support grid,
3...Skeleton, 4...Cell, 5...Fuel rod, 8...
Collar, 9...tube expansion part, 10, 10'...protrusion,
11,11'...stopper.
Claims (1)
ズル、下端に下部ノズルがそれぞれ固着され、前
記制御棒案内シンブルの軸方向に複数個の支持格
子が隔置され、かつ、前記支持格子の格子セルに
燃料棒が挿通され、前記上下部ノズルと前記燃料
棒間に適当な間隙が設けられた原子燃料集合体に
おいて、前記支持格子の前記制御棒案内シンブル
を挿通させる格子セルは格子帯板の巾より長いカ
ラーを備え、前記カラー内に挿通した前記制御棒
案内シンブルと前記カラーとの係合を、最上段支
持格子および最下段支持格子においては機械的結
合あるいは冶金的接合による剛結合とし、前記最
上段および最下段支持格子を除く他の支持格子の
一若しくは二以上においては、前記挿通した制御
棒案内シンブルの軸方向に前記カラーの長さより
大きな間隔で二つの突起を形成し、前記二つの突
起間に前記支持格子を軸方向に摺動可能に受け入
れたことを特徴とする原子燃料集合体。 ２ 前記他の支持格子のうち、最上段支持格子に
最も近い一つの支持格子と前記制御棒案内シンブ
ルとの係合を前記剛結合としたことを特徴とする
特許請求の範囲第１項記載の原子燃料集合体。 ３ 前記他の支持格子のうち燃料集合体軸方向中
央部の一つまたは二つ以上の支持格子と前記制御
棒案内シンブルとの係合を前記剛結合としたこと
を特徴とする特許請求の範囲第１項または第２項
記載の原子燃料集合体。[Scope of Claims] 1. An upper nozzle is fixed to the upper end of a plurality of control rod guide thimbles, and a lower nozzle is fixed to the lower end of the control rod guide thimble, and a plurality of support grids are spaced apart in the axial direction of the control rod guide thimble, and A lattice cell into which the control rod guide thimble of the support lattice is inserted, in a nuclear fuel assembly, in which a fuel rod is inserted into the lattice cell of the support lattice, and an appropriate gap is provided between the upper and lower nozzles and the fuel rod. is provided with a collar that is longer than the width of the grid strip, and the engagement between the control rod guide thimble inserted through the collar and the collar is achieved by mechanical coupling or metallurgical bonding in the uppermost support grid and the lowermost support grid. one or more support grids other than the top and bottom support grids have two protrusions spaced apart from each other by a distance greater than the length of the collar in the axial direction of the inserted control rod guide thimble. A nuclear fuel assembly characterized in that the supporting grid is slidably received in the axial direction between the two protrusions. 2. The control rod guide thimble is engaged with one of the other support grids closest to the uppermost support grid as the rigid connection. Nuclear fuel assembly. 3. Claims characterized in that the engagement between one or more of the other support grids in the axial center of the fuel assembly and the control rod guide thimble is the rigid connection. The nuclear fuel assembly according to item 1 or 2.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56119118A JPS5821193A (en) | 1981-07-31 | 1981-07-31 | Nuclear fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56119118A JPS5821193A (en) | 1981-07-31 | 1981-07-31 | Nuclear fuel assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5821193A JPS5821193A (en) | 1983-02-07 |
| JPS6260039B2 true JPS6260039B2 (en) | 1987-12-14 |
Family
ID=14753371
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56119118A Granted JPS5821193A (en) | 1981-07-31 | 1981-07-31 | Nuclear fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5821193A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2545262B2 (en) * | 1988-03-09 | 1996-10-16 | 原子燃料工業株式会社 | Nuclear fuel assembly |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5546599A (en) * | 1978-09-28 | 1980-04-01 | Exxon Research Engineering Co | Package for semiconductor optoelectronic device |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2337918A1 (en) * | 1976-01-12 | 1977-08-05 | Commissariat Energie Atomique | NUCLEAR FUEL ASSEMBLY |
-
1981
- 1981-07-31 JP JP56119118A patent/JPS5821193A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5546599A (en) * | 1978-09-28 | 1980-04-01 | Exxon Research Engineering Co | Package for semiconductor optoelectronic device |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5821193A (en) | 1983-02-07 |
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