JPH01178894A - Nuclear fuel assembly - Google Patents
Nuclear fuel assemblyInfo
- Publication number
- JPH01178894A JPH01178894A JP63001593A JP159388A JPH01178894A JP H01178894 A JPH01178894 A JP H01178894A JP 63001593 A JP63001593 A JP 63001593A JP 159388 A JP159388 A JP 159388A JP H01178894 A JPH01178894 A JP H01178894A
- Authority
- JP
- Japan
- Prior art keywords
- thimble
- fuel assembly
- control rod
- rod guide
- 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
- 239000003758 nuclear fuel Substances 0.000 title claims description 4
- 239000000446 fuel Substances 0.000 claims abstract description 42
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 6
- 238000005452 bending Methods 0.000 abstract description 14
- 230000003292 diminished effect Effects 0.000 abstract 1
- 238000000034 method Methods 0.000 abstract 1
- 239000013078 crystal Substances 0.000 description 7
- 239000000463 material Substances 0.000 description 5
- 230000000712 assembly Effects 0.000 description 4
- 238000000429 assembly Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 238000007689 inspection Methods 0.000 description 4
- 230000000737 periodic effect Effects 0.000 description 3
- 229910001093 Zr alloy Inorganic materials 0.000 description 2
- 238000002485 combustion reaction Methods 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 238000002441 X-ray diffraction Methods 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000000691 measurement method Methods 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 238000004904 shortening 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)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は原子燃料集合体、特に集合体曲がりの軽減され
た加圧水型原子炉用燃料集合体に関するものである。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a nuclear fuel assembly, and particularly to a fuel assembly for a pressurized water reactor in which assembly curvature is reduced.
（従来の技術）
加圧水型原子炉用燃料集合体（Ａ）は基本的に第１図、
第２図に示すように１４行、１４列の外、１７行、１７
列に配列された多数の燃料棒（１）を上部ノズル（２）
と下部ノズル（３）間で並列し、複数の支持格子（４）
で支持せしめると共に燃料棒（１）の間の所定位置およ
び中心部に夫々制御棒案内シンブル（５）。(Prior art) The fuel assembly (A) for a pressurized water reactor is basically shown in Figure 1.
As shown in Figure 2, outside the 14th row and 14th column, the 17th row and 17th
A large number of fuel rods (1) arranged in rows are connected to the upper nozzle (2).
and a plurality of support grids (4) in parallel between the lower nozzle (3) and the lower nozzle (3).
and a control rod guide thimble (5) at a predetermined position and centrally between the fuel rods (1), respectively.
計装案内シンブル（６）を置き、炉内運転時には制御棒
、計測棒を夫々挿入することによって構成されている。It is constructed by placing an instrumentation guide thimble (6) and inserting a control rod and a measuring rod respectively during operation inside the reactor.
ところが、かかる燃料集合体（Ａ）は、これを原子炉内
で燃焼すると全体として曲示ることがあり、この曲がり
が大きくなると第４図に示している如くなり、燃料の交
替時の取り出し、装荷にあたり、隣接燃料集合体同士で
支持格子が引っ掛かりを起こしたり、また燃料の隣りに
新しい燃料を挿入する場合の干渉の原因となる。However, when such a fuel assembly (A) is burned in a nuclear reactor, the entire fuel assembly (A) may curve as a whole, and when this curve becomes large, it becomes as shown in FIG. During loading, the support grids may get caught between adjacent fuel assemblies, or cause interference when new fuel is inserted next to the fuel.
そこで現在、これを防ぐため支持格子の上下端やコーナ
ーを内方にまるめ、接触が生じても引掛かりには至らな
いようにすることが行われているが、現状では充分な成
果を挙げるに至っていない。To prevent this, current efforts are being made to round the top and bottom ends and corners of the support grid inward so that even if contact occurs, it will not become caught, but at present it has not achieved sufficient results. Not yet reached.
しかも、このように支持格子の上下端やコーナ−を内方
にまるめることは作業が煩わしいのみな゛らず、冷却材
の流れを害する恐れがあり、好ましくない。とは云え、
現在、燃料集合体自体の設計で曲がりについて考慮がな
されている例は見当たらない。Furthermore, it is not preferable to round the upper and lower ends and corners of the support grid inward in this way, since it is not only cumbersome to work with, but also may impede the flow of the coolant. That said,
Currently, there are no examples in which consideration is given to bending in the design of the fuel assembly itself.
（発明が解決しようとする問題点）
本発明は上述の如き現状に対処し、燃料集合体の曲がり
軽減をはかることを課題とし、特に燃料集合体の設計に
着目することにより酸油がりを小さくし、もって燃料取
扱を容易ならしめ定期検査時の燃料交替作業の短縮化を
もたらすことを目的とするものである。(Problems to be Solved by the Invention) The present invention addresses the above-mentioned current situation and aims to reduce the bending of fuel assemblies.In particular, by focusing on the design of the fuel assemblies, the present invention aims to reduce acid and oil spillage. The purpose of this invention is to make fuel handling easier and to shorten the time required to change fuel during periodic inspections.
（問題点を解決するための手段）
しかして、上記目的を達成する本発明の特徴とするとこ
ろは、特に制御棒案内シンブルの伸びに着目し、集合体
内所要の位置に分散配置された上記シンブルの伸びの均
一化を図るべく、前記加圧水型原子炉用燃料集合体にお
いて、原子炉内で装荷される位置を考慮してＦｚの異な
るシンブル管の集合体内の位置を照射成長量を予測して
配置すること、即ち、燃料集合体で炉心中心側に近い側
に置かれる制御棒案内シンブルのＦｚを大きく、遠い側
に置かれる制御棒案内シンブルのＦｚを小さくし、炉心
中心側のシンブル伸びを抑制し、比較的小ならしめる点
にある。(Means for Solving the Problems) The present invention, which achieves the above object, is characterized by paying particular attention to the elongation of the control rod guide thimble and distributing the thimble at required positions within the assembly. In order to make the elongation uniform, in the fuel assembly for the pressurized water reactor, the amount of irradiation growth is predicted for the position within the assembly of thimble tubes with different Fz, taking into account the loading position in the reactor. In other words, by increasing the Fz of the control rod guide thimble placed on the side closer to the core center in the fuel assembly and decreasing the Fz of the control rod guide thimble placed on the far side, the elongation of the thimble on the core side is reduced. The point is to suppress it and make it relatively small.
ここで、集合体の曲がりは通常、最上部支持格子と、最
下部支持格子の中心を結んだ直線と着目する支持格子の
中心との距離で表わされ、実績としては最大約１０胴程
度である。そして、この集合体曲がりの値は各支持格子
の位置を測定することで求まるが、これは水中テレビ検
査、超音波測定などの手段によって行われる。Here, the bending of the aggregate is usually expressed by the distance between the center of the support grid and the straight line connecting the centers of the uppermost support grid and the lowermost support grid, and in actual practice, the bending of the aggregate is about 10 bodies at most. be. The value of the aggregate curvature is determined by measuring the position of each support grid, and this is done by underwater television inspection, ultrasonic measurement, or other means.
本発明者らは、かかる集合体の曲がりについて関心をも
ち、その要因の究明を試みたところ、集合体の骨格構造
を作っている制御棒案内シンブルの照射成長の差によっ
て生ずることを知見した。The inventors of the present invention were interested in the bending of such an assembly, and upon attempting to investigate the cause thereof, discovered that it is caused by differences in the irradiation growth of the control rod guide thimbles that make up the skeleton structure of the assembly.
つまり、燃焼時、炉心外側は中性子照射量が小さいのに
対し、内側はそれが大きくなる。In other words, during combustion, the amount of neutron irradiation on the outside of the core is small, whereas it is large on the inside.
一般に照射成長は中性子照射量に比例するので炉心中心
側のシンブルは伸び、外側はあまり伸びない。このため
集合体は炉心に対し、第３図実線に示すように曲がり、
この曲がりは同図のように中性子束の勾配が大きい炉心
外側でより大きくなる。In general, irradiation growth is proportional to the amount of neutron irradiation, so the thimble at the center of the core stretches, while the outside does not. Therefore, the assembly bends relative to the core as shown by the solid line in Figure 3.
As shown in the figure, this bending becomes larger outside the core where the gradient of the neutron flux is large.
従って、かかる状況よりして集合体においてその曲がり
を軽減するには集合体内に配置されているシンブルの伸
びを均一にすれば有効であると云える。Therefore, in view of this situation, it can be said that it is effective to make the elongation of the thimble arranged in the assembly uniform in order to reduce the bending in the assembly.
ところで、制御棒案内シンブルの伸び（工当咳シンブル
材の集合組繊、特にＦｚといわれる因子に依存する。By the way, the elongation of the control rod guide thimble depends on the aggregate fibers of the thimble material, especially on a factor called Fz.
Ｆｚとは金属結晶の異方性を定量的に評価するために用
いる集合組織係数で下記のように定義される。Fz is a texture coefficient used to quantitatively evaluate the anisotropy of metal crystals and is defined as follows.
即ち、シンブル材に用いられるα相のジルカロイは稠密
六方晶の結晶構造を有している。六方晶系は結晶異方性
が強く、第５図に示すａ軸とａ軸とでは機械的性質が異
なる。That is, the α-phase Zircaloy used in the thimble material has a close-packed hexagonal crystal structure. The hexagonal crystal system has strong crystal anisotropy, and the mechanical properties are different between the a-axis and the a-axis shown in FIG.
とりわけ、ａ軸は他の方向と異なる挙動を示すため、ａ
軸と直交する（０００１）面の極点図が重要となる。な
お、この場合（０００１）面からはＸ線の回折は得られ
ないので、通常はそれと並行な（０００２）面の回折を
用いた極点図となる。In particular, since the a-axis behaves differently from other directions, a
The pole figure of the (0001) plane perpendicular to the axis is important. In this case, since X-ray diffraction cannot be obtained from the (0001) plane, a pole figure is usually obtained using diffraction from the (0002) plane parallel to the (0001) plane.
そこで、この極点図で表わされる結晶の異方性を定量的
に評価するために用いたのがＦｚ値であり、次式で表わ
される。Therefore, the Fz value was used to quantitatively evaluate the anisotropy of the crystal represented by the pole figure, and is expressed by the following equation.
但し、α、φ； 第５図参照
■ （α、φ）；方位角（α、φ）での特定の結晶面の
Ｘ線強度
かくして、試料表面をＸ線回折すると、叙上の如くその
試料内での六方結晶の向きによって（０００２）面から
の回折Ｘ線が増減するため試料の異方性の性質について
知ることが可能となる。However, α, φ; See Figure 5■ (α, φ); X-ray intensity of a specific crystal plane at an azimuth angle (α, φ). Since the diffracted X-rays from the (0002) plane increase or decrease depending on the orientation of the hexagonal crystal within the sample, it becomes possible to learn about the anisotropic properties of the sample.
一般に制御棒案内シンブルの場合、このＦｚは０゜０５
〜０．０７程度である。Generally, in the case of a control rod guide thimble, this Fz is 0°05
It is about 0.07.
しかして、照射成長は上記Ｆｚ値に依存し、詳しくは１
−３Ｆｚに依存する。Therefore, the irradiation growth depends on the above Fz value, and in detail, 1
-3Fz dependent.
ジルカロイの照射成長はＨｅ５ｋｅｔｈ らによって次
式が提唱されている。For the irradiation growth of Zircaloy, the following formula is proposed by Heketh et al.
Ｇ＝Ａ （１−３Ｆｚ）
ここで、Ｇ；伸び歪、Ａ；定数
Ｆｚ；（０００２）面の注目している方向の集合組織係
数
一方、またＭｕｒｇａ ｔｒｏｙｄらによって上記Ｆｚ
の異なるジルカロイ−２に対して照射成長を行った記録
があり、第６図に示す結果を得ている。図中、実線でＡ
（１−３Ｆｚ）を示すがよく一致することが分かる。そ
して、何れもＦｚが大きい程、照射成長は小さくなって
いる。（なお、Ｍｕｒｇａ ｔｒｏｙｄらは図中の一点
鎖線が最も近似としている。）ところで、前述のように
シンブルの伸びはシンブル材の集合組織、特にＦｚとい
われる上記因子に依存するが、かかるシンブル材の集合
組織は製造条件、例えば圧延による寸法変化量、マンド
レル形状などで調整することができる。従ってＦｚの異
なるシンブルを作り、これを集合体内の各位置に適切に
配置すれば本発明燃料集合体を得ることができる。G=A (1-3Fz) Here, G: elongation strain, A: constant Fz: texture coefficient of the (0002) plane in the direction of interest, and the above Fz by Murga troyd et al.
There is a record that irradiation growth was performed on Zircaloy-2 with different values, and the results shown in FIG. 6 were obtained. In the figure, the solid line indicates A.
(1-3Fz), and it can be seen that they match well. In both cases, the larger the Fz, the smaller the irradiation growth. (Murga troyd et al. use the dashed line in the figure as the closest approximation.) By the way, as mentioned above, the elongation of a thimble depends on the texture of the thimble material, especially the above-mentioned factor called Fz. The texture can be adjusted by manufacturing conditions, such as the amount of dimensional change due to rolling, the shape of the mandrel, etc. Therefore, the fuel assembly of the present invention can be obtained by making thimbles with different Fz and arranging them appropriately at each position within the assembly.
（作用）
以上のように燃料集合体内でＦｚの異なるシンブル管を
照射成長量を予測して炉心中心側にＦｚＯ大なるシンブ
ル材からなるシンブル管を、遠い側、即ち、外側にＦｚ
の小なるシンブル材からなるシンブル管を配置せしめた
ことにより、燃焼中、中性子照射量の多い炉心中心側に
おいても伸びは抑えられ、炉心中心側と外側におけるシ
ンブル管の伸びは均一となり、シンブル管の伸び不均一
より生ずる集合体曲がりを防止せしめる。(Function) As described above, by predicting the amount of irradiation growth of thimble tubes with different Fz in the fuel assembly, thimble tubes made of thimble material with a large FzO are placed on the core center side, and Fz
By arranging the thimble tube made of a small thimble material, elongation is suppressed even on the center side of the core where the amount of neutron irradiation is high during combustion, and the elongation of the thimble tube on the center side and outside of the core is uniform, and the thimble tube This prevents the aggregate from bending due to uneven elongation.
（実施例）
以下、添付図面を参照し、上記本発明の詳細な説明する
。(Example) The present invention will now be described in detail with reference to the accompanying drawings.
第１図、第２図は現在使用されている加圧水型原子炉用
の燃料集合体（Ａ）の１例であるが、上下のノズル（２
）（３）間に多数の燃料棒（１）を配列し、支持格子（
４）によって支持していること、集合体の燃料棒（１）
の間に所要位置で制御棒案内シンブル（５）を配置し、
また中心部に計装案内シンブル（６）を配置して運転時
には夫々制御棒、計測棒を挿入していることは本発明燃
料集合体においても基本的に何ら異なるところはない。Figures 1 and 2 show an example of a fuel assembly (A) for a pressurized water reactor currently in use.
) (3) A large number of fuel rods (1) are arranged between them, and a support grid (
4) Supporting the fuel rods of the assembly (1)
Place the control rod guide thimble (5) at the required position between the
Furthermore, there is basically no difference in the fuel assembly of the present invention in that the instrumentation guide thimble (6) is arranged in the center and the control rod and measurement rod are inserted therein during operation.
しかして、上記構成において、本発明では第２図に示す
ように集合体（Ａ）内断定位置に配置されている前記制
御棒案内シンブル（５）に対し、矢印で示す炉心外側方
向と反対側にある炉心中心側に近い列のシンブル（５ａ
）のＦｚを外側寄りの列のシンブル（５ｂ）のＦｚより
大ならしめている。Therefore, in the above configuration, the present invention is arranged so that, as shown in FIG. The thimble in the row near the center of the core (5a
) is made larger than that of the thimble (5b) in the outer row.
勿論、Ｆｚを大ならしめるとは漸増的よりも階段状が製
作上、通常で、又、このＦｚを大ならしめたシンブル（
５）は炉心中心側の１列に限らず２列（５ａ）（５ｃ）
あるいは３列（５ａ） （５ｃ） （５ｄ）であっても
よい。Of course, in order to increase Fz, it is normal to have a step-like structure rather than a gradual one, and the thimble (
5) is not limited to one row on the core center side, but two rows (5a) (5c)
Alternatively, there may be three rows (5a) (5c) (5d).
要は１つの燃料集合体中におけるシンブルの間において
伸びを均一にすることが肝要であり、これに違背しない
限り適宜の改変は可能である。The important thing is to make the elongation uniform among the thimble in one fuel assembly, and appropriate modifications can be made as long as this does not violate this.
かくして、第３図に示す炉心内における集合体（Ａ）の
曲がりは阻止され、同図点線に示すような状態となって
隣接集合体間の互いの干渉が阻止される。In this way, the bending of the assembly (A) in the core shown in FIG. 3 is prevented, and a state as shown by the dotted line in the figure is created, thereby preventing adjacent assemblies from interfering with each other.
（発明の効果）
本発明は以上のように燃料集合体において、炉心中心側
に配置される制御棒案内シンブルのＦｚを炉心外側寄り
に配置される制御棒案内シンブルのＦｚに比し大ならし
めたものであり、中性子照射量の多い炉心中心側におけ
るシンブルの伸びは抑えられ、その結果、燃料集合体中
のシンブルの伸びは炉心中心側と外側において平均して
均一な伸びとなり、燃料集合体の集合体曲がりを小なら
しめ、定期点検時の燃料交替作業を容易にすると共に、
これが定期点検の短縮化につながり、経済性を有利なら
しめる顕著な効果を奏する。(Effects of the Invention) As described above, the present invention provides a fuel assembly in which the Fz of the control rod guide thimbles disposed toward the center of the reactor core is made larger than the Fz of the control rod guide thimble disposed toward the outside of the core. As a result, the elongation of the thimble on the center side of the core, where the amount of neutron irradiation is high, is suppressed, and as a result, the elongation of the thimble in the fuel assembly becomes uniform on average between the center side and the outside of the core, and the elongation of the thimble in the fuel assembly becomes uniform. This reduces the bending of the assembly, making it easier to change fuel during periodic inspections, and
This leads to shortening of periodic inspections and has a remarkable economical effect.
又、本発明燃料集合体は曲がりが小さくなる結果、燃料
取板中に支持格子を欠けさせたり、破損させることも少
なくなり、安全対策面においても頗る有効である。Furthermore, since the fuel assembly of the present invention has less bending, it is less likely that the support grid in the fuel panel will be chipped or damaged, which is extremely effective in terms of safety measures.
第１図は本発明に係る燃料集合体の基本構成を示す正面
概要図、第２図（イ）は前記第１図の燃料集合体のＸ−
Ｘ線矢視断面図、第２図（ロ）は第２図（イ）に示す集
合体内の制御棒案内シンブルのＦｚ分布図、第３図（イ
）は炉心内における集合体の曲がり状態を示す説明図、
第３図（１１りは炉心内における中性子照射量分布状態
図、第４図は集合体面がりによる燃料集合体干渉態様説
明図、第５図（イ）（０） （１１）は本発明における
Ｆｚ （集合組織）測定法を示す説明図、第６図はＦｚ
と照射成長との関係を示す図表である。
（八）・・・加圧水型原子炉用燃料集合体。
（１）・・・燃料棒、（２）・・・上部ノズル。
（３）・・・下部ノズル、（４）・・・支持格子。
（５）・・・制御棒案内シンブル。
（５ａ）〜（５ｄ）・・・各列の制御棒案内シンブル。
（６）・・・計装案内シンブル。
特許出願人 原子燃料工業株式会社
＝、−
ＹＺ口
（ロ） −そう壬子ＪＴ丁７
第５０
（イ） （ロ） （
ハ）乎
第６図
″［FIG. 1 is a schematic front view showing the basic configuration of a fuel assembly according to the present invention, and FIG. 2 (a) is an X-
A sectional view taken along the X-ray line, Figure 2 (B) shows the Fz distribution of the control rod guide thimble in the assembly shown in Figure 2 (A), and Figure 3 (A) shows the bending state of the assembly in the core. An explanatory diagram showing,
Figure 3 (11) is a state diagram of neutron irradiation distribution in the reactor core, Figure 4 is an explanatory diagram of the fuel assembly interference mode due to assembly face flaring, and Figure 5 (a) (0) (11) is the Fz in the present invention. (texture) An explanatory diagram showing the measurement method, Figure 6 is Fz
FIG. (8) Fuel assembly for pressurized water reactors. (1)...Fuel rod, (2)...Upper nozzle. (3)...Lower nozzle, (4)...Support grid. (5)...Control rod guide thimble. (5a) to (5d) Control rod guide thimble for each row. (6)...Instrumentation guide thimble. Patent applicant Nuclear Fuel Industry Co., Ltd. =, - YZguchi (b) - Mitsuko JT-7 No. 50 (a) (b) (
c) 乎Figure 6'' [
Claims (1)
棒を支持格子により配列支持せしめ、かつ燃料棒の間の
所要位置に制御棒案内シンブルを配置してなる加圧水型
原子炉用の燃料集合体において、前記制御棒案内シンブ
ルにＦｚの異なる少なくとも２種のシンブルを用い、原
子炉内で装荷される位置を考慮して炉心中心側に位置す
るシンブルのＦｚを炉心外側寄りに位置するシンブルの
Ｆｚより大ならしめたことを特徴とする原子燃料集合体
。1. A fuel assembly for a pressurized water reactor, in which a large number of fuel rods arranged in parallel between an upper nozzle and a lower nozzle are arranged and supported by a support grid, and a control rod guide thimble is arranged at a predetermined position between the fuel rods. In the control rod guide thimble, at least two types of thimble with different Fz are used, and considering the loading position in the reactor, the Fz of the thimble located toward the center of the reactor core is set to the Fz of the thimble located toward the outside of the core. A nuclear fuel assembly characterized by being larger than Fz.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63001593A JPH01178894A (en) | 1988-01-07 | 1988-01-07 | Nuclear fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63001593A JPH01178894A (en) | 1988-01-07 | 1988-01-07 | Nuclear fuel assembly |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01178894A true JPH01178894A (en) | 1989-07-17 |
Family
ID=11505808
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63001593A Pending JPH01178894A (en) | 1988-01-07 | 1988-01-07 | Nuclear fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01178894A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7668282B2 (en) | 2001-05-18 | 2010-02-23 | Areva Np Gmbh | Method for assembling a pressurized water reactor core, and reactor core configuration |
-
1988
- 1988-01-07 JP JP63001593A patent/JPH01178894A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7668282B2 (en) | 2001-05-18 | 2010-02-23 | Areva Np Gmbh | Method for assembling a pressurized water reactor core, and reactor core configuration |
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