JPS62104195U - - Google Patents
Info
- Publication number
- JPS62104195U JPS62104195U JP1985196153U JP19615385U JPS62104195U JP S62104195 U JPS62104195 U JP S62104195U JP 1985196153 U JP1985196153 U JP 1985196153U JP 19615385 U JP19615385 U JP 19615385U JP S62104195 U JPS62104195 U JP S62104195U
- Authority
- JP
- Japan
- Prior art keywords
- large number
- reactor fuel
- straps
- slits
- 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
- 230000003014 reinforcing effect Effects 0.000 claims description 6
- 239000003758 nuclear fuel Substances 0.000 claims 3
- 238000010586 diagram Methods 0.000 description 1
- 239000000446 fuel Substances 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
Description
第１図は本考案の第１実施例を示す部分図であ
り、第１図Ａはその底面図、第１図Ｂはその平面
図、第１図Ｃは第１図ＢにおけるＣ―Ｃ線断面図
、第１図Ｄは補強部材の斜視図、第２図は支持格
子の隅部近傍における複数の格子を含む部分平面
図、第３図は本考案の第２実施例を示す部分図で
あり、第３図Ａはその底面図、第３図Ｂはその平
面図、第３図Ｃは第３図ＢにおけるＣ―Ｃ線断面
図、第３図Ｄは補強部材の斜視図、第４図は、本
考案の第３実施例を示す部分図であり、第４図Ａ
はその底面図、第４図Ｂはその平面図、第４図Ｃ
は第４図ＢにおけるＣ―Ｃ線断面図、第４図Ｄは
補強部材の斜視図、第５図は本考案の第４実施例
を示す部分図であり、第５図Ａはその底面図、第
５図Ｂはその平面図、第５図Ｃは第５図Ｂにおけ
るＣ―Ｃ線断面図、第５図Ｄは補強部材の部分斜
視図、第６図は従来の支持格子を示す斜視図であ
る。
１１，２１，３１，４１，５１……ストラツプ
、１２，２２，３２，４２……補強部材、１３，
２３，３３，４３，５３……スプリング、１４，
２４，３４，４４，５４……デインプル、１５，
２５，３５，４５，５５……燃料棒。
Fig. 1 is a partial view showing the first embodiment of the present invention, Fig. 1A is a bottom view thereof, Fig. 1B is a plan view thereof, and Fig. 1C is a line CC line in Fig. 1B. 1D is a perspective view of the reinforcing member, FIG. 2 is a partial plan view including a plurality of grids near the corners of the support grid, and FIG. 3 is a partial view showing a second embodiment of the present invention. Figure 3A is a bottom view, Figure 3B is a top view, Figure 3C is a sectional view taken along line CC in Figure 3B, Figure 3D is a perspective view of the reinforcing member, Figure 4 The figure is a partial view showing the third embodiment of the present invention, and FIG.
is its bottom view, Figure 4B is its top view, and Figure 4C is its bottom view.
is a sectional view taken along the line CC in FIG. 4B, FIG. 4D is a perspective view of the reinforcing member, FIG. 5 is a partial view showing the fourth embodiment of the present invention, and FIG. 5A is a bottom view thereof. , FIG. 5B is a plan view thereof, FIG. 5C is a sectional view taken along line CC in FIG. 5B, FIG. 5D is a partial perspective view of the reinforcing member, and FIG. 6 is a perspective view showing a conventional support grid. It is a diagram. 11, 21, 31, 41, 51... strap, 12, 22, 32, 42... reinforcing member, 13,
23, 33, 43, 53... Spring, 14,
24, 34, 44, 54...Dimple, 15,
25, 35, 45, 55...fuel rods.
Claims (1)
方向に一定間隔毎に多数のスリツトが設けられた
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多
数の格子を形成し、これら各格子に原子炉燃料棒
を挿入して支持するようにした原子炉燃料集合体
の支持格子において、前記格子の相対向する角部
間に補強部材を掛け渡して前記各角部に固着した
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 in which a large number of slits are provided at regular intervals in a direction perpendicular to the longitudinal direction of a rectangular thin plate, the slits of these straps are fitted into each other and assembled vertically and horizontally to form a large number of lattices. In the support grid of the reactor fuel assembly in which the reactor fuel rods are inserted and supported in each of these grids, a reinforcing member is stretched between the opposing corner parts of the grid to provide support at each corner. A support grid for a nuclear reactor fuel assembly, characterized in that it is fixed.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1985196153U JPH023194Y2 (en) | 1985-12-20 | 1985-12-20 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1985196153U JPH023194Y2 (en) | 1985-12-20 | 1985-12-20 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62104195U true JPS62104195U (en) | 1987-07-02 |
| JPH023194Y2 JPH023194Y2 (en) | 1990-01-25 |
Family
ID=31154711
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1985196153U Expired JPH023194Y2 (en) | 1985-12-20 | 1985-12-20 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH023194Y2 (en) |
-
1985
- 1985-12-20 JP JP1985196153U patent/JPH023194Y2/ja not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPH023194Y2 (en) | 1990-01-25 |
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