JPH0220717Y2 - - Google Patents
Info
- Publication number
- JPH0220717Y2 JPH0220717Y2 JP1985151868U JP15186885U JPH0220717Y2 JP H0220717 Y2 JPH0220717 Y2 JP H0220717Y2 JP 1985151868 U JP1985151868 U JP 1985151868U JP 15186885 U JP15186885 U JP 15186885U JP H0220717 Y2 JPH0220717 Y2 JP H0220717Y2
- Authority
- JP
- Japan
- Prior art keywords
- spring
- strap
- straps
- slits
- 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
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
- Springs (AREA)
- Butt Welding And Welding Of Specific Article (AREA)
Description
【考案の詳細な説明】
[産業上の利用分野]
本考案は原子炉燃料集合体の支持格子に係り、
特に該支持格子を構成するストラツプの板厚を増
大することなく、支持格子の強度を増すことがで
きるものに関する。[Detailed description of the invention] [Industrial application field] The present invention relates to a support grid for a nuclear reactor fuel assembly.
In particular, the invention relates to something that can increase the strength of the support grid without increasing the thickness of the straps that make up the support grid.
[従来の技術]
原子炉に装荷されている燃料集合体は、第2図
に示されるように構成されている。[Prior Art] A fuel assembly loaded in a nuclear reactor is constructed as shown in FIG.
即ち、この燃料集合体は第2図において図中上
下に離間して平行に配設された上部ノズル1及び
下部ノズル2と、これらの間に所定の間隔をおい
て配設された複数の支持格子3と、第3図に示さ
れるようにこれら支持格子3に形成された多数の
格子空間4における所定の格子空間5を挿通して
前記上部ノズル1及び下部ノズル2にそれぞれそ
の上下端部が連結されて燃料集合体の骨組みを構
成する制御棒案内管6と、前記支持格子3の所定
の格子空間7内に挿通して第4図に示されるよう
にスプリング8及びデインプル9によつて支持さ
れているとともにその内部に多数の燃料ペレツト
10及び押さえバネ11が密封されている複数の
燃料棒12とから構成されている。 That is, as shown in FIG. 2, this fuel assembly includes an upper nozzle 1 and a lower nozzle 2 arranged parallel to each other and spaced apart from each other vertically in the figure, and a plurality of supports arranged at predetermined intervals between them. The upper and lower ends of the upper and lower nozzles 1 and 2 are inserted through the grid 3 and predetermined grid spaces 5 in a large number of grid spaces 4 formed in these support grids 3, as shown in FIG. A control rod guide tube 6 which is connected to form the framework of a fuel assembly is inserted into a predetermined lattice space 7 of the support lattice 3 and supported by a spring 8 and a dimple 9 as shown in FIG. The fuel rod 12 has a large number of fuel pellets 10 and a pressure spring 11 sealed therein.
このような燃料集合体の支持格子3は、第5図
に示されるストラツプ13を多数縦横に組み込む
ことにより形成されている。 The support grid 3 of such a fuel assembly is formed by incorporating a large number of straps 13 shown in FIG. 5 vertically and horizontally.
即ち、このストラツプ13は、長方形状の薄い
耐熱合金板をその長手方向と直角な方向に切り込
んで多数のスリツト14を形成し、これら各スリ
ツト間に前記合金板の一方の側に該合金板の一部
を突出させてスプリング8を形成するとともに、
このスプリング8の両側部を打ち抜いてスロツト
15を形成し、更に、このスプリング8の第5図
における上下に位置する部位の一部を前記合金板
の一方の側にそれぞれ突出させてデインプル9を
形成してなるものである。 That is, this strap 13 is made by cutting a rectangular thin heat-resistant alloy plate in a direction perpendicular to its longitudinal direction to form a large number of slits 14, and between each of these slits there is a section of the alloy plate on one side of the alloy plate. While forming a spring 8 by protruding a part,
Slots 15 are formed by punching out both sides of the spring 8, and dimples 9 are formed by partially protruding upper and lower portions of the spring 8 to one side of the alloy plate in FIG. This is what happens.
第6図は上記ストラツプ13を租み込んで形成
した支持格子3の一部破断斜視図である。 FIG. 6 is a partially cutaway perspective view of the support grid 3 formed by enclosing the straps 13.
[考案が解決しようとする問題点]
このような従来の支持格子にあつては、前記ス
プリング8及びスロツト15の近傍の強度が他の
部分に比較して弱くなりがちであり、これを補う
めに他の部分の強度を不必要に強くしなければな
らないという不都合が生じていた。[Problems to be solved by the invention] In such a conventional support grid, the strength near the spring 8 and the slot 15 tends to be weak compared to other parts. This has caused the inconvenience of having to make other parts unnecessarily strong.
即ち、前記スロツト15の大きさは冷却水の循
環を確保し、燃料棒12等の冷却を十分なものと
する観点から一定以上でなければならないととも
に、前記スプリング8はその形成の際に引きのば
されて他の部分よりも薄くなつており、それ故こ
れらスロツト15及びスプリング8の近傍は殆ど
強度的寄与を期待出来ないものだからである。 That is, the size of the slot 15 must be larger than a certain value from the viewpoint of ensuring circulation of cooling water and sufficient cooling of the fuel rods 12, etc., and the spring 8 must be designed so that the spring 8 has no tension when formed. This is because the area near the slot 15 and the spring 8 can hardly be expected to contribute to the strength because it is extended and thinner than other parts.
この強度を補うには、前記ストラツプ13自体
の板厚を厚くすればよいが、そうすると、スプリ
ング8のバネ定数や格子間隔が変化し、燃料集合
体の設計変更を余儀なくされ、望ましくない。 In order to compensate for this strength, the thickness of the strap 13 itself may be increased, but this would change the spring constant and lattice spacing of the spring 8, which would undesirably necessitate a change in the design of the fuel assembly.
更に、板厚が厚くなればストラツプの加工がよ
り難しくなる。 Furthermore, the thicker the plate, the more difficult it is to process the strap.
本考案の目的は、上記欠点を除去した原子炉燃
料集合体の支持格子を得ることにある。 The object of the present invention is to obtain a support grid for a nuclear reactor fuel assembly that eliminates the above-mentioned drawbacks.
[問題点を解決するための手段]
本考案は、長方形状を有する薄板にその長手方
向と直角な方向に一定間隔毎に多数の切り込みを
入れてスリツトを形成し、これら各スリツト間に
前記薄板の一部を一方の側に突出させてスプリン
グを形成するとともに該スプリングの両側部を打
き抜いてスロツトを形成してなるストラツプを多
数用いてこれらストラツプの前記スリツトを互い
に嵌め合わせて縦横に組んで格子状に形成した原
子炉燃料集合体の支持格子において、
前記ストラツプの前記スプリングの両端部に補
強板を、それぞれ前記ストラツプの長手方向に沿
つて、かつ前記スプリングの中央部及び前記両ス
ロツトを横切つて取り付け、前記各補強板の中央
部にねじりを加えたものである。[Means for Solving the Problems] The present invention involves forming a large number of slits in a rectangular thin plate at regular intervals in a direction perpendicular to its longitudinal direction, and inserting the thin plate between each of these slits. A part of the straps are made to protrude to one side to form a spring, and both sides of the spring are punched out to form slots.The straps are assembled vertically and horizontally by fitting the slits of these straps into each other. In the support lattice of a nuclear reactor fuel assembly formed in a lattice shape, reinforcing plates are provided at both ends of the spring of the strap, respectively, along the longitudinal direction of the strap, and at the center of the spring and both the slots. The reinforcing plates are attached horizontally and twisted at the center of each of the reinforcing plates.
[作用]
本考案の原子炉燃料集合体の支持格子にあつて
は、補強板によつて、スプリングの両端部のスト
ラツプ及び両スロツトの側部のストラツプの強度
を補強することにより、ストラツプ全体を厚くし
なくても十分な強度の支持格子を得ることができ
る。[Function] In the support grid of the reactor fuel assembly of the present invention, the strength of the straps at both ends of the spring and the straps at the sides of both slots is reinforced by the reinforcing plate, thereby increasing the strength of the entire strap. A support grid with sufficient strength can be obtained without increasing the thickness.
[実施例]
第1図は本考案の一実施例の一部破断斜視図で
ある。[Embodiment] FIG. 1 is a partially cutaway perspective view of an embodiment of the present invention.
第1図において、符号13aは縦横に組まれて
支持格子を形成するストラツプであり、これら各
ストラツプ13aには第1図に示されるように、
該ストラツプの一部を一方の側、即ち図中紙面後
方側に突出させて形成されたスプリング8a及び
このスプリング8aの両側部を打ち抜いて形成さ
れたスロツト15aが設けられているとともに、
これらスプリング8a及びスロツト15aの上下
の部位には前記ストラツプ13aの一部を紙面手
前側に突出させて形成されたデインプル9aが設
けられている。 In FIG. 1, the reference numeral 13a indicates straps that are assembled vertically and horizontally to form a support grid, and each of these straps 13a has, as shown in FIG.
A spring 8a is formed by projecting a part of the strap toward one side, that is, the rear side of the paper in the figure, and a slot 15a is formed by punching out both sides of the spring 8a.
Dimples 9a formed by projecting a portion of the strap 13a toward the front in the drawing are provided above and below the spring 8a and the slot 15a.
又、前記ストラツプ13aのスプリング8aの
両端部に補強板16がそれぞれ前記ストラツプ1
3aの長手方向に沿つて取り付けられ、前記スト
ラツプ13aに補強板16が前記スプリング8a
の中央部(突出部)及び前記両スロツト15aを
横切つて取り付けられている。そして、前記3枚
の補強板16の中央部にはねじりが加えられてい
る。 Further, reinforcing plates 16 are provided at both ends of the spring 8a of the strap 13a, respectively.
A reinforcing plate 16 is attached to the strap 13a along the longitudinal direction of the spring 8a.
It is attached across the central part (protrusion) of the slot 15a and both the slots 15a. The center portions of the three reinforcing plates 16 are twisted.
前記実施例にあつては、以下の利点がある。 The above embodiment has the following advantages.
即ち、強度が弱いスプリング8a及びスロツト
15aの近傍が補強板16によつて補強されてい
るから、ストラツプ13a全体を厚くすることな
く支持格子全体の強度を十分なものとすることが
できる。 That is, since the vicinity of the spring 8a and the slot 15a, which have weak strength, are reinforced by the reinforcing plate 16, the strength of the entire support grid can be made sufficient without increasing the thickness of the entire strap 13a.
又、補強板16で補強板されているから、スロ
ツト15aの大きさを十分なものにしても強度的
に問題となることはない。 Further, since the reinforcing plate 16 is used as a reinforcing plate, there is no problem in terms of strength even if the slot 15a is made sufficiently large.
更に、前記補強板16に加えられたねじれ部に
よつて、補強効果が一層高まるとともに、冷却水
を有効に乱流となすことができ、冷却効果を大幅
に向上させることができる。 Furthermore, the twisted portion added to the reinforcing plate 16 further enhances the reinforcing effect, and also makes it possible to effectively make the cooling water a turbulent flow, thereby significantly improving the cooling effect.
[考案の効果]
以上詳述したように、本考案は長方形状を有す
る薄板にその長手方向と直角な方向に一定間隔毎
に多数の切り込みを入れてスリツトを形成し、こ
れら各スリツト間に前記薄板の一部を一方の側に
突出させてスプリングを形成するとともに該スプ
リングの両側部を打ち抜いてスロツトを形成して
なるストラツプを多数用いてこれらストラツプの
前記スリツトを互いに嵌め合わせて縦横に組んで
格子状に形成した原子炉燃料集合体の支持格子に
おいて、
前記ストラツプの前記スプリングの両端部に補
強板をそれぞれ前記ストラツプの長手方向に沿つ
て取り付け、前記ストラツプに補強板を前記スプ
リングの中央部及び前記両スロツトを横切つて取
り付け、前記各補強板の中央部にねじりを加えた
ものであるから、補強板によつて、スプリングの
両端部のストラツプ及び両スロツトの側部のスト
ラツプの強度を補強することにより、ストラツプ
全体を厚くしなくても十分な強度の支持格子を得
ることができる上、補強板の中央部にねじりを加
えることにより、補強効果を一層高めることがで
きるとともに、燃料集合体装荷状態において冷却
水を有効に乱流となすことができ、冷却効果を大
幅に向上させることができる。[Effects of the invention] As detailed above, the present invention involves forming a large number of slits in a rectangular thin plate at regular intervals in a direction perpendicular to its longitudinal direction, and forming the slits between each of these slits. A spring is formed by making a part of a thin plate protrude on one side, and a number of straps are formed by punching out both sides of the spring to form slots, and the slits of these straps are fitted into each other to form a spring. In the support lattice of a reactor fuel assembly formed in a lattice shape, reinforcing plates are attached to both ends of the spring of the strap along the longitudinal direction of the strap, and reinforcing plates are attached to the strap at the center part of the spring and Since the reinforcing plates are attached across both slots and twisted at the center, the reinforcing plates reinforce the strength of the straps at both ends of the spring and the straps at the sides of both slots. By doing so, it is possible to obtain a support grid with sufficient strength without increasing the thickness of the entire strap, and by adding twist to the center of the reinforcing plate, the reinforcing effect can be further enhanced, and the fuel assembly In the loaded state, the cooling water can be effectively made into a turbulent flow, and the cooling effect can be greatly improved.
第1図は本考案の一実施例を示す一部破断斜視
図、第2図は原子炉燃料集合体を示す図、第3図
は第2図の−線断面図、第4図は第3図の一
部拡大図、第5図はストラツプを示す図、第6図
は従来の原子炉燃料集合体の支持格子を示す一部
破断斜視図である。
8a……スプリング、13a……ストラツプ、
15a……スロツト、16……補強板。
Fig. 1 is a partially cutaway perspective view showing an embodiment of the present invention, Fig. 2 is a view showing a nuclear reactor fuel assembly, Fig. 3 is a sectional view taken along the line - - of Fig. FIG. 5 is a partially enlarged view of the figure, FIG. 5 is a view showing a strap, and FIG. 6 is a partially cutaway perspective view showing a support grid of a conventional nuclear reactor fuel assembly. 8a...Spring, 13a...Strap,
15a...Slot, 16...Reinforcement plate.
Claims (1)
方向に一定間隔毎に多数の切り込みを入れてスリ
ツトを形成し、これら各スリツト間に前記薄板の
一部を一方の側に突出させてスプリングを形成す
るとともに該スプリングの両側部を打ち抜いてス
ロツトを形成してなるストラツプを多数用いてこ
れらストラツプの前記スリツトを互いに嵌め合わ
せて縦横に組んで格子状に形成した原子炉燃料集
合体の支持格子において、 前記ストラツプの前記スプリングの両端部に補
強板を、それぞれ前記ストラツプの長手方向に沿
つて、かつ前記スプリングの中央部及び前記両ス
ロツトを横切つて取り付け、前記各補強板の中央
部にねじりを加えたことを特徴とする原子炉燃料
集合体の支持格子。[Claims for Utility Model Registration] A number of cuts are made in a rectangular thin plate at regular intervals in a direction perpendicular to its longitudinal direction to form slits, and a part of the thin plate is placed between each of the slits on one side. A nuclear reactor in which a large number of straps are formed by protruding to the side to form a spring and punching out both sides of the spring to form slots, and the slits of these straps are fitted into each other and assembled vertically and horizontally to form a lattice shape. In the support grid of the fuel assembly, reinforcing plates are attached to both ends of the spring of the strap, respectively, along the longitudinal direction of the strap, and across the center of the spring and both slots, and each reinforcing plate is attached to each end of the spring of the strap. A support grid for a nuclear reactor fuel assembly characterized by a twist in the center of the plate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1985151868U JPH0220717Y2 (en) | 1985-10-03 | 1985-10-03 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1985151868U JPH0220717Y2 (en) | 1985-10-03 | 1985-10-03 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6259891U JPS6259891U (en) | 1987-04-14 |
| JPH0220717Y2 true JPH0220717Y2 (en) | 1990-06-05 |
Family
ID=31069325
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1985151868U Expired JPH0220717Y2 (en) | 1985-10-03 | 1985-10-03 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0220717Y2 (en) |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS51151492A (en) * | 1975-06-20 | 1976-12-25 | Nuclear Fuel Ind Ltd | Spacer grid for nuclear fuel assemblies |
| JPS54142485A (en) * | 1978-04-28 | 1979-11-06 | Mitsubishi Atom Power Ind Inc | Grid for fuel assembly |
-
1985
- 1985-10-03 JP JP1985151868U patent/JPH0220717Y2/ja not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6259891U (en) | 1987-04-14 |
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