JPH022980A - Support lattice - Google Patents

Support lattice

Info

Publication number
JPH022980A
JPH022980A JP63149342A JP14934288A JPH022980A JP H022980 A JPH022980 A JP H022980A JP 63149342 A JP63149342 A JP 63149342A JP 14934288 A JP14934288 A JP 14934288A JP H022980 A JPH022980 A JP H022980A
Authority
JP
Japan
Prior art keywords
strap
edge
outer strap
inclined plate
plate
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
Application number
JP63149342A
Other languages
Japanese (ja)
Other versions
JPH067185B2 (en
Inventor
Akio Oriuchi
折内 章男
Akihiro Kato
明博 加藤
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Mitsubishi Nuclear Fuel Co Ltd
Original Assignee
Mitsubishi Nuclear Fuel Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Mitsubishi Nuclear Fuel Co Ltd filed Critical Mitsubishi Nuclear Fuel Co Ltd
Priority to JP63149342A priority Critical patent/JPH067185B2/en
Publication of JPH022980A publication Critical patent/JPH022980A/en
Publication of JPH067185B2 publication Critical patent/JPH067185B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Stringed Musical Instruments (AREA)

Abstract

PURPOSE:To improve mechanical strength and contrive the prevention of damage by forming a neck part of an inclined plate formed on both the edges in the width direction of an outer strap and a reinforcing plate on which the edge part formed on the inclined plate is joined with an inner strap. CONSTITUTION:A thin-plate beltlike outer strap 12 is provided on the surroundings of a lattice body 10, side taps 11a are inserted in slits 12a formed on the face of the outer strap 12 and the tabs 11a projected from the slits 12a are seam-welded. A neck part 15 is formed along the longitudinal direction of the outer strap 12 on both the edge parts in the width direction of the outer strap 12. The cross section of the neck part 15 is doglegged and the neck part 15 is integratedly formed on the edge part of the outer strap 12. Further it is integratedly formed on the edge part of an inclined plate 16 and the inclined plate 16 and a reinforcing plate 17 for extending toward the edge part in the width direction of inner straps 11 from the edge part thereof are formed. The intersecting points of the edge parts of the reinforcing plate 17 and the inner straps 11 are spot-welded and further the inclined plate 16 is positioned between the longitudinally contacting slits 12 to form.

Description

【発明の詳細な説明】 「産業上の利用分野」 この発明は、加圧水型軽水炉等の原子炉に装荷される核
燃料集合体の支持格子に関するものである。
DETAILED DESCRIPTION OF THE INVENTION "Field of Industrial Application" The present invention relates to a support grid for a nuclear fuel assembly loaded into a nuclear reactor such as a pressurized water reactor.

「従来の技術」 周知のように、核燃料集合体には、第3図に示すように
、上下方向に離間して対向配置された上部ノズル1と下
部ノズル2との間に、複数の制御棒案内管3が渡されて
固定され、これら制御棒案内管3の中途部に、多数の燃
料棒4を支持するための複数の支持格子5が上下方向に
互いに離間して取り付けられている。
"Prior Art" As is well known, in a nuclear fuel assembly, as shown in FIG. Guide tubes 3 are passed and fixed, and a plurality of support grids 5 for supporting a large number of fuel rods 4 are attached at midpoints of these control rod guide tubes 3 at a distance from each other in the vertical direction.

上記支持格子5は、第4図および第5図に示すように、
長手方向両端部にサイドタブ6a、6aが形成された薄
板帯状の内ストラップ6を互いに直交させて正方格子状
の格子本体7を形成し、この格子本体7の四周に薄板帯
状の外ストラップ8をこれに形成されたスリット8a、
8aに上記サイドタブ6a、6aを挿入し、このスリッ
ト8 a、 8 aから突出したサイドタブ6 a、 
6 aの一部を折り曲げて外ストラップ8を仮止めした
後、これらをろう付けし、次いで上記突出したサイドタ
ブ6a、6aを研削除去することにより組み立てられた
ものである。
The support grid 5, as shown in FIGS. 4 and 5,
Inner straps 6 in the form of thin plate strips with side tabs 6a, 6a formed at both ends in the longitudinal direction are made perpendicular to each other to form a grid body 7 in the form of a square lattice, and outer straps 8 in the form of thin plate bands are arranged around the four circumferences of this grid body 7. a slit 8a formed in
The side tabs 6a, 6a are inserted into the slits 8a, and the side tabs 6a protrude from the slits 8a, 8a.
After bending a part of the outer strap 6a and temporarily fixing the outer strap 8, these parts are brazed, and then the protruding side tabs 6a, 6a are removed by grinding.

また、上記外ストラップ8の幅方向の両縁部には、上記
内ストラップG側に傾斜するベーン8bが外ストラップ
8の長手方向に所定間隔で形成されている。このベーン
8bは、原子炉内における冷却水の撹拌を促進すると共
に、原子炉内に多数の核燃料集合体を出し入れする際に
、隣接する核燃料集合体に支持格子5の外ストラップ8
の縁部が干渉して、核燃料集合体同士が引っ掛かり合っ
たり、あるいは、損傷するのを防止するためのものであ
る。
Further, vanes 8b that are inclined toward the inner strap G side are formed at predetermined intervals in the longitudinal direction of the outer strap 8 at both edges in the width direction of the outer strap 8. This vane 8b promotes agitation of cooling water in the reactor, and also attaches the outer strap 8 of the support grid 5 to adjacent nuclear fuel assemblies when taking a large number of nuclear fuel assemblies in and out of the reactor.
This is to prevent the edges of the nuclear fuel assemblies from interfering with each other and causing them to become caught or damaged.

[発明が解決しようとする課題] ところで、原子炉内においては、その稼動時に下方から
上方に向けて勢いよく冷却水が循環しており、この冷却
水が上記ベーン8bに激しく衝突する。このベーン8b
は縁部が自由端になっているので、その機械的強度が冷
却水の圧力に耐えきれず、ベーン8bがその屈曲部等か
らちぎれてしまい、冷却水中に異物として混入する恐れ
がある。
[Problems to be Solved by the Invention] In the nuclear reactor, during operation, cooling water circulates vigorously from below to above, and this cooling water violently collides with the vanes 8b. This vane 8b
Since the edges of the vanes 8b are free ends, their mechanical strength cannot withstand the pressure of the cooling water, and there is a risk that the vanes 8b may be torn off from their bent portions, resulting in contamination of the cooling water as foreign matter.

このように、冷却水中に異物が混入すると、核燃料集合
体を傷付ける等の問題が生じる。
In this way, if foreign matter gets mixed into the cooling water, problems such as damage to the nuclear fuel assembly will occur.

また、上記支持格子5においては、その外周部の機械的
強度が内部に比べて低いので、外周部が座屈し易いとい
う欠点もあった。
Furthermore, the support grid 5 has a disadvantage in that the outer circumferential portion is easily buckled because the mechanical strength of the outer circumferential portion thereof is lower than that of the inner portion.

この発明は上記課題を解決することをその目的としてい
る。
This invention aims to solve the above problems.

「課題を解決するための手段」 この発明の支持格子は、外ストラップの幅方向の両縁部
に、同外ストラップの長手方向に沿い、かつ水抜孔が形
成された縁部を形成し、この縁部を、外ストラップの両
縁部に形成され、かつ内ストラップ側に向けて傾斜した
傾斜板と、この傾斜板の長手方向の縁部に内ストラップ
に向けて形成され、かつ縁部が内ストラップの幅方向の
縁部に接合された補強板とにより構成したものである。
"Means for Solving the Problems" The support grid of the present invention has edges formed with drainage holes along the longitudinal direction of the outer strap at both edges in the width direction of the outer strap. An inclined plate formed on both edges of the outer strap and inclined toward the inner strap side, and an inclined plate formed on the longitudinal edge of this inclined plate toward the inner strap and whose edge is inner. The reinforcing plate is connected to the edge of the strap in the width direction.

「作用 」 この発明の支持格子にあっては、外ストラップの幅方向
の両縁部に形成された傾斜板の縁部に補強板を形成し、
この補強板の縁部を内ストラップに接合したので、これ
ら傾斜板と補強板とにより構成される縁部の機械的強度
が従来のベーンより格段に向上し、よって縁部の破損を
防止することができる。
"Function" In the support grid of the present invention, reinforcing plates are formed at the edges of the inclined plates formed at both edges in the width direction of the outer strap,
Since the edge of this reinforcing plate is joined to the inner strap, the mechanical strength of the edge formed by these inclined plates and the reinforcing plate is significantly improved compared to conventional vanes, thereby preventing damage to the edge. I can do it.

また、縁部により外ストラップの機械的強度(特に座屈
強度)が向上し、しかも縁部を構成する補強板の縁部が
内ストラップに接合されているので、支持格子全体の機
械的強度(特に座屈強度)が向上する。
In addition, the mechanical strength (especially buckling strength) of the outer strap is improved by the edge, and since the edge of the reinforcing plate that makes up the edge is joined to the inner strap, the mechanical strength of the entire support grid ( In particular, buckling strength) is improved.

さらに、縁部に衝突する冷却水の一部が水抜孔を通過す
るので、縁部に作用する冷却水の圧力が軽減され、よっ
てこの点においても縁部の破損を防止することができる
Further, since a portion of the cooling water that collides with the edge passes through the drain hole, the pressure of the cooling water acting on the edge is reduced, and damage to the edge can also be prevented in this respect.

[実施例j 以下この発明の支持格子の一実施例を第1図および第2
図を参照して説明する。
[Embodiment j] An embodiment of the support grid of the present invention will be described below with reference to FIGS. 1 and 2.
This will be explained with reference to the figures.

これらの図において符号lOは格子本体を示す。In these figures, the symbol lO indicates the grating body.

この格子本体10は、複数の薄板帯状の内ストラップ1
1を互いに直交させて正方格子状に組んだものであり、
各内ストラップ11の長手方向両端中央部には、サイド
タブllaがストラップ11の幅方向に沿って形成され
ている。
This lattice main body 10 includes a plurality of inner straps 1 in the form of thin strips.
1 are arranged perpendicularly to each other in the form of a square grid,
Side tabs lla are formed along the width direction of the strap 11 at the center portions of both longitudinal ends of each inner strap 11 .

上記格子本体10の四周には、薄板帯状をなす外ストラ
ップ12が、その面に形成されたスリット12aに上記
サイドタブllaを挿入し、このスリット12aから突
出したサイドタブIlaをシーム溶接することにより取
り付けられている。
An outer strap 12 in the form of a thin plate band is attached to the four circumferences of the lattice main body 10 by inserting the side tab Ila into a slit 12a formed on the surface thereof and seam welding the side tab Ila protruding from the slit 12a. ing.

上記外ストラップ12の幅方向の両縁部には、縁部15
が外ストラップ12の長手方向に沿って形成されている
。この縁部15は断面路(字状のものであり、外ストラ
ップ12の縁部に一体的に形成されて、内ストラップi
l側に向けて傾斜する傾斜板16と、この傾斜板16の
縁部に一体的に形成されて、この縁部から上記内ストラ
ップllの幅方向の縁部に向けて延びる補強板17とか
ら構成されている。この補強板17の縁部と内ストラッ
プ1にの縁部との交点はスポット溶接されている。また
、上記傾斜板16には長方形状の水抜孔18が傾斜板1
6の長手方向において上記隣接するスリット12aの間
に位置させて形成されている。
Edges 15 are provided at both edges in the width direction of the outer strap 12.
is formed along the longitudinal direction of the outer strap 12. This edge 15 has a cross-sectional shape, is formed integrally with the edge of the outer strap 12, and is formed integrally with the edge of the inner strap i.
An inclined plate 16 that is inclined toward the l side, and a reinforcing plate 17 that is integrally formed on the edge of this inclined plate 16 and extends from this edge toward the edge of the inner strap 11 in the width direction. It is configured. The intersection of the edge of the reinforcing plate 17 and the edge of the inner strap 1 is spot welded. In addition, a rectangular drainage hole 18 is provided in the inclined plate 16.
6 is located between the adjacent slits 12a in the longitudinal direction.

上記構成の支持格子によれば、冷却水の撹拌を促進する
と共に、原子炉内に多数の核燃料集合体を出し入れする
際における、核燃料集合体同士の干渉を防止する従来の
ベーン8aの役割を果たす振部15を、外ストラップ1
2の縁部に一体的に形成された傾斜板16と、この傾斜
板16に一体的に形成されて縁部が内ストラップ11に
スポット溶接された補強板17とにより構成したので、
振部15の機械的強度が従来のベーン8aより格段に向
上する。したがって、原子炉内において、冷却水の圧力
により振部15が破損するのを防止することができるの
で、冷却水中に振部15の破片が混入することに起因す
る問題を解消することができる。
According to the support grid having the above configuration, it plays the role of the conventional vane 8a, which not only promotes agitation of the cooling water but also prevents interference between nuclear fuel assemblies when a large number of nuclear fuel assemblies are taken in and out of the reactor. The swing part 15 is attached to the outer strap 1.
2, and a reinforcing plate 17 that is integrally formed with the inclined plate 16 and whose edge is spot welded to the inner strap 11.
The mechanical strength of the swinging portion 15 is significantly improved compared to the conventional vane 8a. Therefore, it is possible to prevent the shaking part 15 from being damaged by the pressure of the cooling water in the nuclear reactor, so it is possible to solve the problem caused by the fragments of the shaking part 15 getting mixed into the cooling water.

また、上記振部15により外ストラップ12の機械的強
度(特に座屈強度)が向上し、しかも振部15を構成す
る補強板17の縁部が内ストラップ11に溶接されてお
り、さらには内ストラップ11と外ストラップ12とを
スリット12aから突出しているサイドタブllaを溶
接することにより接合したので、支持格子全体の機械的
強度(特に座屈壷度)が従来に比べ格段に向上し、その
結果、核燃料集合体の耐震、座屈強度が向上する。
In addition, the mechanical strength (especially buckling strength) of the outer strap 12 is improved by the swinging part 15, and the edge of the reinforcing plate 17 constituting the swinging part 15 is welded to the inner strap 11. Since the strap 11 and the outer strap 12 are joined by welding the side tab lla protruding from the slit 12a, the mechanical strength (especially the buckling strength) of the entire support grid is significantly improved compared to the conventional one. , the earthquake resistance and buckling strength of nuclear fuel assemblies are improved.

さらに、振部15を構成する傾斜板17に水抜孔18を
形成したので、原子炉内において、振部15に衝突する
冷却水の一部がこの水抜孔18を通過して循環する。し
たがって、振部15に作用する冷却水の圧力が軽減され
るので、この点においても振部15の破損を防止するこ
とができる。
Further, since the water drain hole 18 is formed in the inclined plate 17 constituting the swing section 15, a part of the cooling water that collides with the swing section 15 passes through the water drain hole 18 and circulates within the reactor. Therefore, the pressure of the cooling water acting on the vibrating portion 15 is reduced, and damage to the vibrating portion 15 can also be prevented in this respect.

「発明の効巣」 以上説明したように、この発明によれば、冷却水の撹拌
を促進すると共に、原子炉内に多数の核燃料集合体を出
し入れする際における、核燃料集合体同士の干渉を防止
するための振部を、外ストラップの幅方向の両縁部に形
成された傾斜板と、この傾斜板に形成されて縁部が内ス
トラップに接合された補強板、とにより構成したので、
振部の機械的強度が従来のベーンより格段に向上する。
"Effects of the Invention" As explained above, according to the present invention, stirring of cooling water is promoted and interference between nuclear fuel assemblies is prevented when a large number of nuclear fuel assemblies are taken in and out of a nuclear reactor. The oscillation part for this purpose is composed of an inclined plate formed on both edges in the width direction of the outer strap, and a reinforcing plate formed on this inclined plate and whose edges are joined to the inner strap.
The mechanical strength of the swing part is significantly improved compared to conventional vanes.

したがって、原子炉内において、冷却水の圧力により振
部が破損するのを防止することができるので、冷却水中
に振部の破片が混入することに起因する問題を解消する
ことができる。
Therefore, it is possible to prevent the shaking part from being damaged by the pressure of the cooling water in the nuclear reactor, so it is possible to solve problems caused by pieces of the shaking part getting mixed into the cooling water.

また、振部により外ストラップの機械的強度(特に座屈
強度)が向上し、しかも振部を構成する補強板の縁部が
内ストラップに接合されているので、支持格子全体の機
械的強度(特に座屈強度)が従来に比べ格段に向上し、
その結果、核燃料集合体の耐震、座屈強度が向上する。
In addition, the mechanical strength (especially buckling strength) of the outer strap is improved by the swing part, and since the edge of the reinforcing plate that makes up the swing part is joined to the inner strap, the mechanical strength of the entire support grid ( In particular, the buckling strength) has been significantly improved compared to conventional
As a result, the earthquake resistance and buckling strength of the nuclear fuel assembly are improved.

さらに、振部に水抜孔を形成したので、原子炉内におい
て、振部に衝突する冷却水の一部がこの水抜孔を通過し
て循環する。したがって、振部に作用する冷却水の圧力
が軽減されるので、この点においても振部の破損を防止
することができる。
Furthermore, since a water drain hole is formed in the shaking part, a part of the cooling water that collides with the shaking part passes through the water drain hole and circulates inside the reactor. Therefore, since the pressure of the cooling water acting on the swinging section is reduced, damage to the swinging section can also be prevented in this respect.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図および第2図はこの発明の支持格子の一実施例を
示すものであり、第1図は支持格子の要部を示す概略斜
視図、第2図は支持格子の要部の断面図、第3図は核燃
料集合体の正面図、第4図および第5図は従来の支持格
子の一例を示すものであり、第4図は支持格子の斜視図
、第5図は組立途中の支持格子の要部の斜視図である。 lO・・・・・・格子本体、11・・・・・・内ストラ
ップ、12・・・・・・外ストラップ、15・・・・・
・振部、16・・・・・・傾斜板、17・・・・・・補
強板、18・・・・・・水抜孔。
1 and 2 show an embodiment of the support grid of the present invention, FIG. 1 is a schematic perspective view showing the main parts of the support grid, and FIG. 2 is a sectional view of the main parts of the support grid. , Fig. 3 is a front view of a nuclear fuel assembly, Figs. 4 and 5 show an example of a conventional support grid, Fig. 4 is a perspective view of a support grid, and Fig. 5 is a support during assembly. It is a perspective view of the main part of a lattice. lO... Lattice body, 11... Inner strap, 12... Outer strap, 15...
- Shaking part, 16... Inclined plate, 17... Reinforcement plate, 18... Water drain hole.

Claims (2)

【特許請求の範囲】[Claims] (1)複数の薄板帯状の内ストラップを互いに交差させ
てなる格子本体の外周を薄板帯状の外ストラップで囲ん
でなる支持格子において、 上記外ストラップの幅方向の両縁部に、同外ストラップ
の長手方向に沿う襟部を形成してなり、この襟部が、上
記外ストラップの両縁部に形成され、かつ上記内ストラ
ップ側に向けて傾斜した傾斜板と、この傾斜板の長手方
向の縁部に上記内ストラップに向けて形成され、かつ縁
部が上記内ストラップの幅方向の縁部に接合された補強
板とにより構成されていることを特徴とする支持格子。
(1) In a support lattice in which the outer periphery of a lattice main body formed by intersecting a plurality of inner straps in the form of thin plate bands is surrounded by an outer strap in the form of a thin plate band, the outer straps are attached to both edges in the width direction of the outer straps. A collar portion extending in the longitudinal direction is formed, and the collar portion is formed at both edges of the outer strap and includes an inclined plate inclined toward the inner strap side, and an edge in the longitudinal direction of the inclined plate. A support grid comprising: a reinforcing plate formed toward the inner strap at a portion thereof, and a reinforcing plate having an edge joined to an edge in the width direction of the inner strap.
(2)上記襟部に水抜孔を形成したことを特徴とする特
許請求の範囲第1項に記載の支持格子。
(2) The support grid according to claim 1, characterized in that a drainage hole is formed in the collar.
JP63149342A 1988-06-17 1988-06-17 Support grid Expired - Lifetime JPH067185B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63149342A JPH067185B2 (en) 1988-06-17 1988-06-17 Support grid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63149342A JPH067185B2 (en) 1988-06-17 1988-06-17 Support grid

Publications (2)

Publication Number Publication Date
JPH022980A true JPH022980A (en) 1990-01-08
JPH067185B2 JPH067185B2 (en) 1994-01-26

Family

ID=15473017

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63149342A Expired - Lifetime JPH067185B2 (en) 1988-06-17 1988-06-17 Support grid

Country Status (1)

Country Link
JP (1) JPH067185B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2003073435A3 (en) * 2002-02-27 2004-01-15 Framatome Anp Gmbh Spacer for a fuel element of a boiling water reactor
JP2009526977A (en) * 2006-02-18 2009-07-23 アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング Fuel assemblies for pressurized water reactors

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2003073435A3 (en) * 2002-02-27 2004-01-15 Framatome Anp Gmbh Spacer for a fuel element of a boiling water reactor
US7555093B1 (en) 2002-02-27 2009-06-30 Areva Np Gmbh Spacer for a fuel assembly of a boiling water reactor
JP2009526977A (en) * 2006-02-18 2009-07-23 アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング Fuel assemblies for pressurized water reactors

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