JPS59164980A - Nuclear fuel assembly - Google Patents
Nuclear fuel assemblyInfo
- Publication number
- JPS59164980A JPS59164980A JP58039033A JP3903383A JPS59164980A JP S59164980 A JPS59164980 A JP S59164980A JP 58039033 A JP58039033 A JP 58039033A JP 3903383 A JP3903383 A JP 3903383A JP S59164980 A JPS59164980 A JP S59164980A
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel assembly
- cladding tube
- heat transfer
- amount
- 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
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
- Fuel-Injection Apparatus (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) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、核燃料棒の熱的現象に係り、特に、燃料棒の
伝熱社全増加させる事に好的な燃料棒形状に係る。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to the thermal phenomena of nuclear fuel rods, and more particularly to a fuel rod shape that is favorable for increasing the heat transfer rate of the fuel rod.
従来の核燃料棒の被覆管内面は、平滑であり、伝熱面積
が限られていたため伝熱量（ペレットから被覆管）とし
ても制限があった。The inner surface of the cladding tube of conventional nuclear fuel rods was smooth, and the heat transfer area was limited, so the amount of heat transfer (from the pellet to the cladding tube) was also limited.
しかし伝熱量が小さいままであればペレット内部温度は
上昇し、ペレットの割れ等のような欠点が生じる。However, if the amount of heat transfer remains small, the internal temperature of the pellet will rise, causing defects such as cracking of the pellet.
本発明の目的は、照射を受ける核燃料棒において、ペレ
ット割れ等をなくシ、伝熱量を増大させる事によシ炉内
効率を高める事の出来る核燃料集合体を提供するもので
ある。An object of the present invention is to provide a nuclear fuel assembly that can improve in-core efficiency by eliminating pellet cracking and increasing the amount of heat transfer in nuclear fuel rods subjected to irradiation.
伝熱量は伝熱面積に比例し増加するという事実に基き、
被覆管内周面に凹凸を設けることにより、ペレットから
被覆管への伝熱量を増加させる核燃料集合体を与える。Based on the fact that the amount of heat transfer increases in proportion to the heat transfer area,
By providing unevenness on the inner peripheral surface of the cladding tube, a nuclear fuel assembly is provided in which the amount of heat transferred from the pellets to the cladding tube is increased.
本発明の実施例として第１図、第２図を示して説明する
。第１図に沸騰水型原子炉に使用される燃料集合体の例
を示す。An embodiment of the present invention will be described with reference to FIGS. 1 and 2. Figure 1 shows an example of a fuel assembly used in a boiling water reactor.
核燃料集合体は正方格子状に複数個配列された燃料棒４
が、下部タイプレート２と上部タイプレート１によって
保持され、さらに支持格子５によって燃料棒相互の間隔
ｄを維持している。The nuclear fuel assembly consists of a plurality of fuel rods 4 arranged in a square lattice.
are held by the lower tie plate 2 and the upper tie plate 1, and the spacing d between the fuel rods is maintained by the support grid 5.
第２図に、第１図中の燃料棒４の断面を示す。FIG. 2 shows a cross section of the fuel rod 4 in FIG. 1.
被覆管内周面には、図のように燃料棒軸方向に直角に螺
旋状の溝が切られている。As shown in the figure, a spiral groove is cut into the inner peripheral surface of the cladding tube at right angles to the axial direction of the fuel rod.
伝熱量が、伝熱面積に正比例するとすれば、高さ０．１
ｖａｎの尚さ金持ち６０度の傾きを持つ山状の溝を切
る事によシ、溝を切らない状態よりも２倍近い伝熱面積
（伝熱量）を持つ事にな込。If the amount of heat transfer is directly proportional to the heat transfer area, then the height is 0.1
By cutting a mountain-shaped groove with an inclination of 60 degrees, the heat transfer area (heat transfer amount) is almost twice as large as that without cutting the groove.
又、製造時においても被覆管内面を、被加工物である被
覆管内面を同様の凸凹の形状を持つ治具を用い容易に加
工する事が出来る。Further, during manufacturing, the inner surface of the cladding tube can be easily processed using a jig having the same uneven shape as the inner surface of the cladding tube, which is a workpiece.
被覆管内面に螺旋状の凹凸の溝を掘るという、簡単な構
造によシペレットから被覆管への伝熱量全増大する事が
出来る。The total amount of heat transferred from the pellet to the cladding tube can be increased by a simple structure of digging a spiral groove on the inner surface of the cladding tube.
第１図は燃料集合体の概略図、第２図は核燃料棒説明図
である。
１・・・上部タイプレート、２・・・下部タイプレート
、３・・・チャンネルボックス、４・・・燃料棒、５丁
・支持格子、６・・・被覆管、７・・・ペレット、８・
・・螺旋状凹凸被覆管内面。
代理人 弁理士 高橋明夫
め１図
牟 ２ 目FIG. 1 is a schematic diagram of a fuel assembly, and FIG. 2 is an explanatory diagram of a nuclear fuel rod. DESCRIPTION OF SYMBOLS 1... Upper tie plate, 2... Lower tie plate, 3... Channel box, 4... Fuel rod, 5 rods/support grid, 6... Cladding tube, 7... Pellet, 8・
・Inner surface of cladding tube with spiral irregularities. Agent Patent Attorney Akio Takahashi 1 Figure 2
Claims (1)
によシ成る核燃料棒において、金属性円筒内周面に多数
の螺旋状の凹凸を設けたことを特徴とする核燃料集合体
。1. A nuclear fuel assembly comprising a nuclear fuel rod consisting of cylindrical pellets of nuclear fuel material and a metallic cylindrical cladding tube, characterized in that a large number of spiral irregularities are provided on the inner peripheral surface of the metallic cylinder.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58039033A JPS59164980A (en) | 1983-03-11 | 1983-03-11 | Nuclear fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58039033A JPS59164980A (en) | 1983-03-11 | 1983-03-11 | Nuclear fuel assembly |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS59164980A true JPS59164980A (en) | 1984-09-18 |
Family
ID=12541796
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58039033A Pending JPS59164980A (en) | 1983-03-11 | 1983-03-11 | Nuclear fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59164980A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4942014A (en) * | 1986-08-15 | 1990-07-17 | United Kingdom Atomic Energy Authority | Nuclear fuel pin fabrication |
-
1983
- 1983-03-11 JP JP58039033A patent/JPS59164980A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4942014A (en) * | 1986-08-15 | 1990-07-17 | United Kingdom Atomic Energy Authority | Nuclear fuel pin fabrication |
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