JPS6352093A - Support lattice for reactor fuel aggregate - Google Patents
Support lattice for reactor fuel aggregateInfo
- Publication number
- JPS6352093A JPS6352093A JP61196778A JP19677886A JPS6352093A JP S6352093 A JPS6352093 A JP S6352093A JP 61196778 A JP61196778 A JP 61196778A JP 19677886 A JP19677886 A JP 19677886A JP S6352093 A JPS6352093 A JP S6352093A
- Authority
- JP
- Japan
- Prior art keywords
- strap
- support grid
- sleeve
- reactor fuel
- grid
- 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
Links
- 239000003758 nuclear fuel Substances 0.000 title claims description 5
- 239000000446 fuel Substances 0.000 description 10
- 238000010586 diagram Methods 0.000 description 5
- 238000000034 method Methods 0.000 description 4
- 230000003014 reinforcing effect Effects 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 238000005219 brazing Methods 0.000 description 1
- 238000005352 clarification Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000002787 reinforcement Effects 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
- Physical Or Chemical Processes And Apparatus (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
「産業上の利用分野」
この発明は、値数の然料欅を支持する瞑子炉燃料集合体
の支持格子に関する。DETAILED DESCRIPTION OF THE INVENTION "Industrial Application Field" The present invention relates to a support grid for a cylindrical reactor fuel assembly that supports a large number of natural fuel assemblies.
「従来の技術」
従来、このイ（の１痕子炉、檀料嗅合体の支持格子とし
て第６図ないし第Ｓ図に示すものが知らｎている。``Prior Art'' Hitherto, the support grids shown in FIGS. 6 to S are known as support lattices for the 1-in-1 test furnace and the danryo-olfactory unit.
Ｔｇ６図において、符号ｌは燃料集合体である。In the Tg6 diagram, the symbol l is a fuel assembly.
燃料集合体ｌは、上下に水平に隔てらｎた上部ノズル２
と、下ＭＳノズル８と、こｎもの間に配電さｎた支持格
子ルと、支持格子もの後述するスＩＪ ＋プを通して上
部ノズル２及び下部ノズル８を連結する制御＊＄、内管
５と、支持格子もの後述する格子空間を１融って配設さ
ｎた燃料棒６とを具備してなるものである。The fuel assembly l has an upper nozzle 2 separated horizontally from top to bottom.
, the lower MS nozzle 8, a support grid with power distributed between them, and a control linking the upper nozzle 2 and the lower nozzle 8 through the support grid, which will be described later, and the inner pipe 5. The support grid is also provided with fuel rods 6 arranged in a grid space, which will be described later.
支持格子４ｒｉ、第り図に示すような長方形状の薄板に
その長手方向と直角な方向に一定間隔ごとにスリット７
が形成さｎたストラップ８を用いて、スリット７を瓦に
嵌め合わせて縦号黄に組んで、第Ｓ図のように多数の格
子空間９が形成さｎたものである。格子空間９には、あ
る間隔をおいて格子空間９とＩＩＩ線を一致させて円筒
形のスリーブＩＯが装着されている。The support grid 4ri is a rectangular thin plate as shown in Figure 1, with slits 7 arranged at regular intervals in a direction perpendicular to its longitudinal direction.
The slits 7 are fitted into the roof tiles using the straps 8 formed with the slits 8 and assembled vertically to form a large number of lattice spaces 9 as shown in Fig. S. A cylindrical sleeve IO is installed in the grid space 9 with a certain interval and the line III coincides with the grid space 9.
上記構成からなる支持格子４は、スリーブＬＯに制御棒
案内管５を挿通し、この制御棒案内管５をスリーブｌＯ
にＩ１１定して燃料集合体ｌの骨組をになるよう支持す
るものである。The support grid 4 having the above structure has a control rod guide tube 5 inserted into the sleeve LO, and a control rod guide tube 5 inserted into the sleeve LO.
The framework of the fuel assembly 1 is supported with a fixed I11.
「発明が解決しようとする問題点」
ところで、従来の支持格子４は、燃料果合体を構成する
状態において、スリーブｌＯを装着した部分の外側の強
度が内側に対して弱いという欠点があつ走。``Problems to be Solved by the Invention'' By the way, the conventional support grid 4 has a drawback in that, when forming a fuel assembly, the outside strength of the part where the sleeve 1O is attached is weaker than the inside strength.
すなわち、スリーブＩＯを装着した部分の内側は、スリ
ーブｌＯを通して制御−条内ｆ５が配設さｎており、制
御棒案内管が補強部材となる丸め強度が強くなり、外側
は、制御棒案内管が無いためｆＦ３側に比べて相対的に
強度が弱くなる、スリーブＩＯ＋７）装着された部分の
外側の強度を補うには、ストラップ８の板厚を厚くすｎ
ばよいが、そうすると、中性子吸収材を増やすことにな
って原子炉ｄ’ｆｉ経済上望ましくないという問題が生
じる。That is, on the inside of the part where the sleeve IO is attached, the control rod guide tube f5 is arranged through the sleeve IO, and the control rod guide tube serves as a reinforcing member, increasing the rounding strength, and on the outside, the control rod guide tube Because there is no fF3 side, the strength is relatively weak compared to the fF3 side. To compensate for the strength of the outside of the part where the sleeve IO + 7) is attached, increase the thickness of the strap 8.
This would be fine, but this would increase the number of neutron absorbers, which would be undesirable from the economic point of view of the nuclear reactor d'fi.
本発明は、支持格子４において、スリーブＩＯの装着さ
ｎた６分の外側の強度が弱いという欠点を、全体のスト
ラップ８の板厚の増加を抑えていかにして改善するかを
問題にしている。The present invention solves the problem of how to improve the weak strength of the support grid 4 on the outside where the sleeve IO is attached by suppressing the increase in the thickness of the entire strap 8. There is.
「間ね点を解決するための手段」
この発明は、原子炉燃料果合体の支持格子において、装
着されるスリーブの最外側部に位置するストラップを基
準として、その内側より外側のストラップの板厚を厚く
したものである。``Means for solving the gap point'' The present invention is based on the strap located at the outermost part of the sleeve to be installed in the support grid of the reactor fuel assembly, and the plate thickness of the outer strap than the inner side. It is made thicker.
「夾施例」
第１図ないし第３図は、この発明の一実施例を示す図で
ろる。第１図において、ｍｔ図の構成要素と同一の要素
には同一の符号を付し、その脱明を省略する。"Embodiment" FIGS. 1 to 3 are diagrams showing an embodiment of the present invention. In FIG. 1, the same elements as those in the mt diagram are given the same reference numerals, and their clarification will be omitted.
この第１図に示す支持格子１１が第Ｓ図に示す支持格子
もと異なる点は、支持格子の内側と外測とでストラップ
の板厚が異なる点である。すなわち、支持格子１１は、
支持格子１１に装着されたスリーブ１０の最外１則部に
位置するストラップを基準にして内側部１２とこの内側
部１２よりストラップの板厚の厚い外側部１８とを具備
してなるものでるる。The support grid 11 shown in FIG. 1 differs from the support grid shown in FIG. S in that the straps have different thicknesses on the inside and outside of the support grid. That is, the support grid 11 is
It comprises an inner part 12 based on the strap located at the outermost part of the sleeve 10 attached to the support grid 11, and an outer part 18 where the strap is thicker than the inner part 12. .
内０（１部１２は、第２図に示すように縦ストラップ１
４と慣ストラップ１５を用いて、従来例と同様にして縦
ストラップ１４と横ストラップ１５をそｎ−ｅｎｎ縦転
組んで格子状に形成してなるものである。縦ストラップ
１４及び横ストラップ１５には、長手方向の両端部に長
手方向に延びる板片状の継手１！！１ｓ１６が形成さｎ
ている。Inside 0 (1 part 12 is the vertical strap 1 as shown in Figure 2)
4 and a customary strap 15, the vertical strap 14 and the horizontal strap 15 are vertically twisted to form a lattice shape in the same manner as in the conventional example. The vertical strap 14 and the horizontal strap 15 have plate-shaped joints 1 extending in the longitudinal direction at both longitudinal ends! ! 1s16 formed n
ing.
外側部１８は、第３図に示すように縦ストラップ１７と
横ストラップＬ８を用いて、従来列と同様にして縦スト
ラップ１７と横ストラップ１８とをそれぞＡｄ横に組ん
で格子状に形成してなるものである。また、外側部１Ｂ
の内部には、開口部１９が形成されている。縦ストラッ
プ１７及び横ストラップ１８の長さの短い短ストラップ
２０には、長手方向に延びる板片状の継手部２１が形成
されている。As shown in FIG. 3, the outer part 18 is formed into a lattice shape by using the vertical straps 17 and the horizontal straps L8 and assembling the vertical straps 17 and the horizontal straps 18 horizontally in the same manner as in the conventional row. That's what happens. In addition, the outer part 1B
An opening 19 is formed inside. A short strap 20 having a shorter length than the vertical strap 17 and the horizontal strap 18 is formed with a plate-shaped joint portion 21 extending in the longitudinal direction.
内Ｉ！１１部１２と外１１１１部１８は、第９図、第Ｓ
図に示すように、内１１１部１２のストラップと外側部
１８のストラップとの厚さ方向の中心を一致させて継手
１！６１６と継手部２１とが組み合わさｎ、これらの継
手！１ｓ１６と継手部２１とをろう付等で結合すること
により連結さｎている。Inside I! 11 part 12 and outer 1111 part 18 are shown in Fig. 9, S
As shown in the figure, the joint 1! 616 and the joint part 21 are assembled by aligning the centers in the thickness direction of the strap of the inner 111 part 12 and the strap of the outer part 18, and these joints! 1s16 and the joint portion 21 are connected by brazing or the like.
継手部１６と継手ｇ（Ｓ２１とを組み合わせる第１の方
法は、第９図に示すように礪手部１６を継手ｇ２１の１
部４１面と外側部１８のストラップのスリット７の間に
挿入しこの継手部１６を外囲部１８のストラップの外側
面に沿って折り曲げ、継手部２１を外側部ｌＢのストラ
ップの内−１ｉｆｉに沿って折り曲げる方法である。第
２の方法は、第Ｓ図に示すように継手部１６を硼手部２
１の・側面と外側部１８のストラップのスリット７の間
に挿入する方法である。The first method of combining the joint portion 16 and the joint g (S21) is to connect the grooved portion 16 to one of the joints g21 as shown in FIG.
The joint part 16 is inserted between the surface of the part 41 and the slit 7 of the strap of the outer part 18, and the joint part 16 is bent along the outer surface of the strap of the outer part 18, and the joint part 21 is inserted into the inner part of the strap of the outer part 1B. This is a method of folding along the The second method is to connect the joint part 16 to the girder part 2 as shown in FIG.
This is a method of inserting the strap between the side surface and the slit 7 of the outer part 18.
上記構成からなる支持格子１１によれば、外側ｔｌ’１
ｓｌＢのストラップの板厚を内側部１２より厚くしたか
ら、支持格子１１を燃料果合体ｌに組み込んだ時に、内
側部１２に対して相対的に弱くなる外Ｘｌｌｌｌ部１８
を補強することができ、全体のストラツブの板厚を厚く
することなく支持格子１１の全体の強度を十分なものに
することができる。したがって、外！！１１部１８の補
強に対してストラップの板厚の増加を最小限に抑えるこ
とができるので、支持格子１１の価格の上昇を最小限に
抑えることができる。According to the support grid 11 having the above configuration, the outer side tl'1
Since the thickness of the strap of slB is made thicker than the inner part 12, when the support grid 11 is assembled into the fuel assembly l, the outer part 18 becomes relatively weaker than the inner part 12.
can be reinforced, and the overall strength of the support grid 11 can be made sufficient without increasing the thickness of the entire strut. Therefore, outside! ! Since the increase in the thickness of the strap for reinforcing the 11 portion 18 can be minimized, an increase in the price of the support grid 11 can be minimized.
「発明の効果」
この発明によｎば、原子炉娯科集合体の支持格子におい
て、装着されるスリーブの最外側部に位置するストラッ
プを基準としてその内側より外側のストラップの板厚を
厚くシ九から、支持格子を燃料集合体に組込んだ時に支
持格子の上記内側に対して相対的に強度の弱くなる上記
外側のストラップを補強することができ、全体のストラ
ップの板厚を厚くすることなく支持格子の全体の’ＦＪ
ＪＪｔを十分なものにすることができる。したがって
、上記外側のストラップの補強に対してストラップの板
厚の僧加を最小限に抑えることができるので、支持格子
の価格の上昇を最小限に抑えることができる。"Effects of the Invention" According to the present invention, in the support grid of a nuclear reactor entertainment assembly, the thickness of the outer strap is thicker than that of the inner strap, based on the strap located at the outermost part of the sleeve to be attached. From 9th, when the support grid is incorporated into the fuel assembly, the outer strap, which has a relatively weaker strength than the inner side of the support grid, can be reinforced, and the thickness of the entire strap can be increased. Whole 'FJ' of support grid without
JJt can be made sufficient. Therefore, it is possible to minimize the increase in the thickness of the strap with respect to the reinforcement of the outer strap, and therefore it is possible to minimize the increase in the price of the support grid.
第１図はこの発明の一実施例として示した支持格子の平
面図、第２図は同支持格子の内９１１部を示す斜視図、
’ＩＩ、３図は同支持格子の外１３１１ｍを示す斜視図
、繁参図、第５図は同支持格子の礪手部の組み合わせ方
を示す説明図、第６図は燃料集合体を示す正面図、第７
図は支持格子を構成するストラップを示す正面図、第ｆ
図は従来の支持格子を示す平面図である。
ｌ・・・・・・燃料果合体、４．１１・・・・・・支持
格子、？・・・・・・スリット、８・・・・・・ストラ
ップ、９・・・・・・格子空間、１０・・・・・・スリ
ーブ。
４七ニア′
第６図FIG. 1 is a plan view of a support grid shown as an embodiment of the present invention, and FIG. 2 is a perspective view showing the inner 911 part of the support grid.
'II, Figure 3 is a perspective view showing the outer 1311m of the support grid, a reference diagram, Figure 5 is an explanatory diagram showing how to combine the grooves of the support grid, and Figure 6 is a front view showing the fuel assembly. Figure, 7th
The figure is a front view showing the straps that make up the support grid, part f.
The figure is a plan view showing a conventional support grid. l...Fuel combination, 4.11...Support grid, ? ...Slit, 8...Strap, 9...Lattice space, 10...Sleeve. 47nia' Figure 6
Claims (1)
定間隔ごとに多数の切込みを入れてスリットを形成して
なるストラップを多数用いて、これらのストラップの上
記スリットを互いに嵌め合わせて縦横に組んで多数の格
子空間を形成し、これらの格子空間のいずれかと軸線を
一致させて円円筒形のスリーブが装着される原子炉燃料
集合体の支持格子において、装着されるスリーブの最外
側部に位置するストラップを基準として、その内側より
外側のストラップの板厚を厚くしたことを特徴とする原
子炉燃料集合体の支持格子。Using a large number of straps formed by forming slits by making a number of cuts at regular intervals in a rectangular thin plate in a direction perpendicular to its longitudinal direction, the slits of these straps are fitted into each other and assembled vertically and horizontally. In the support grid of a reactor fuel assembly, a cylindrical sleeve is installed with its axis aligned with one of these grid spaces, forming a large number of grid spaces, and located at the outermost part of the sleeve to be installed. A support grid for a nuclear reactor fuel assembly, characterized in that the outer strap is thicker than the inner strap, with the outer strap being thicker than the inner strap.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61196778A JPS6352093A (en) | 1986-08-22 | 1986-08-22 | Support lattice for reactor fuel aggregate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61196778A JPS6352093A (en) | 1986-08-22 | 1986-08-22 | Support lattice for reactor fuel aggregate |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6352093A true JPS6352093A (en) | 1988-03-05 |
| JPH0511873B2 JPH0511873B2 (en) | 1993-02-16 |
Family
ID=16363475
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61196778A Granted JPS6352093A (en) | 1986-08-22 | 1986-08-22 | Support lattice for reactor fuel aggregate |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6352093A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20220028265A (en) * | 2020-08-28 | 2022-03-08 | 한전원자력연료 주식회사 | Inconel spacer grid of a nuclear fuel assembly |
-
1986
- 1986-08-22 JP JP61196778A patent/JPS6352093A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20220028265A (en) * | 2020-08-28 | 2022-03-08 | 한전원자력연료 주식회사 | Inconel spacer grid of a nuclear fuel assembly |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0511873B2 (en) | 1993-02-16 |
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