JPH0319994U - - Google Patents
Info
- Publication number
- JPH0319994U JPH0319994U JP1989079405U JP7940589U JPH0319994U JP H0319994 U JPH0319994 U JP H0319994U JP 1989079405 U JP1989079405 U JP 1989079405U JP 7940589 U JP7940589 U JP 7940589U JP H0319994 U JPH0319994 U JP H0319994U
- Authority
- JP
- Japan
- Prior art keywords
- tie plate
- fuel assembly
- inflow
- boiling water
- prevents
- 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
- 239000000446 fuel Substances 0.000 claims description 8
- 238000009835 boiling Methods 0.000 claims description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 5
- 239000002826 coolant Substances 0.000 claims 2
- 239000000463 material Substances 0.000 claims 2
- 125000006850 spacer group Chemical group 0.000 claims 2
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000011218 segmentation 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
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Description
第１図、第２図は、本考案に係る沸騰水型原子
炉用燃料集合体の下部タイプレートを示す各別実
施例の平面図、第３図は上記下部タイプレートの
異種実施例による平面図、第４図は第３図の部分
拡大斜視図、第５図は従来の沸騰水型原子炉用燃
料集合体を示す一部切欠の縦断正面略示図、第６
図は同上集合体の下部タイプレートを示した平面
図で、第７図は第６図の−線縦断要部正面図
である。
１……チヤンネルボツクス、２……上部タイプ
レート、３……下部タイプレート、３ａ……支持
受筒、３ｂ……上面プレート、３ｃ……連結腕、
３ｄ……支持格子体、３ｅ……流入口、１０……
分割用腕、１１……細分化流入口。
1 and 2 are plan views of different embodiments of the lower tie plate of a fuel assembly for a boiling water reactor according to the present invention, and FIG. 3 is a plan view of a different embodiment of the lower tie plate. 4 is a partially enlarged perspective view of FIG. 3, FIG. 5 is a partially cutaway schematic front view showing a conventional boiling water reactor fuel assembly, and FIG.
This figure is a plan view showing the lower tie plate of the same assembly as above, and FIG. 7 is a front view of the main part taken along the line -- in FIG. 6. 1...Channel box, 2...Upper tie plate, 3...Lower tie plate, 3a...Support receiver, 3b...Top plate, 3c...Connection arm,
3d...Support grid body, 3e...Inflow port, 10...
Division arm, 11...Segmentation inlet.
Claims (1)
イプレートと下部タイプレートとの間に、所要本
数の燃料棒が引揃え状態にて縦装支持され、これ
らの燃料棒が、長手方向に所要間隔だけ離して設
けられたスペーサにより、所定の相互間隔を保持
され、前記下部タイプレートには、その上面プレ
ートに燃料棒の下部端栓を装入支持する多数の支
持受筒と、これらを連設した多数の連結腕とによ
り形成されている支持格子体にあつて、多数開口
された冷却材の流入口が、これを所要数に分割す
る分割用腕の跨設によつて、多数の細分化流入口
に区分されてなる異物の流入を阻止した沸騰水型
原子炉用燃料集合体。 (2) 細分化流入口が、スペーサの具備している
冷却材の流通口よりも小さい請求項(1)記載の異
物の流入を阻止した沸騰水型原子炉用燃料集合体
。 (3) 分割用腕が、下部タイプレートの上面プレ
ート、支持受筒、連結腕による支持格子体と、同
材にて一体、または別材にて別体に形成され、か
つ上記連結腕と平行、または斜交状に形成されて
いる請求項(1)記載の異物の流入を阻止した沸騰
水型原子炉用燃料集合体。[Claims for Utility Model Registration] (1) Surrounded by a channel box, a required number of fuel rods are vertically supported in alignment between an upper tie plate and a lower tie plate, and these fuel rods are The rods are maintained at a predetermined distance from each other by spacers provided at a predetermined distance in the longitudinal direction, and the lower tie plate has a number of supports for inserting and supporting the lower end plugs of the fuel rods on the upper plate thereof. In a support lattice body formed by a receiving tube and a large number of connecting arms connecting the receiving tubes, a plurality of coolant inlets having a plurality of openings straddle dividing arms that divide the receiving tube into the required number. A fuel assembly for a boiling water reactor that prevents the inflow of foreign matter by dividing into a large number of subdivided inlets. (2) The fuel assembly for a boiling water nuclear reactor that prevents the inflow of foreign matter according to claim (1), wherein the segmented inlet is smaller than the coolant flow port provided in the spacer. (3) The dividing arm is made of the same material as the upper plate of the lower tie plate, the support tube, and the support grid made up of the connecting arms, or is formed separately from a different material, and is parallel to the connecting arm. 2. The fuel assembly for a boiling water nuclear reactor which prevents the inflow of foreign matter according to claim (1), wherein the fuel assembly is formed in a diagonal shape.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1989079405U JPH0319994U (en) | 1989-07-05 | 1989-07-05 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1989079405U JPH0319994U (en) | 1989-07-05 | 1989-07-05 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0319994U true JPH0319994U (en) | 1991-02-27 |
Family
ID=31623538
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1989079405U Pending JPH0319994U (en) | 1989-07-05 | 1989-07-05 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0319994U (en) |
-
1989
- 1989-07-05 JP JP1989079405U patent/JPH0319994U/ja active Pending
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