JPS6326797Y2 - - Google Patents
Info
- Publication number
- JPS6326797Y2 JPS6326797Y2 JP1983100294U JP10029483U JPS6326797Y2 JP S6326797 Y2 JPS6326797 Y2 JP S6326797Y2 JP 1983100294 U JP1983100294 U JP 1983100294U JP 10029483 U JP10029483 U JP 10029483U JP S6326797 Y2 JPS6326797 Y2 JP S6326797Y2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- plenum
- nuclear
- spring
- plenum spring
- 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.)
- Expired
Links
- 239000008188 pellet Substances 0.000 claims description 27
- 239000000446 fuel Substances 0.000 claims description 25
- 239000003758 nuclear fuel Substances 0.000 claims description 9
- 238000005253 cladding Methods 0.000 claims description 8
- 238000003466 welding Methods 0.000 description 5
- 238000004519 manufacturing process Methods 0.000 description 4
- 230000004992 fission Effects 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 238000004804 winding Methods 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【考案の詳細な説明】
本考案は、被覆管内に多数個の燃料ペレツトを
充填し、その燃料ペレツトと端栓との間にプレナ
ムスプリングを介装した原子炉用核燃料要素に係
り、特にそのプレナムスプリング部の改良に関す
る。[Detailed description of the invention] The present invention relates to a nuclear fuel element for a nuclear reactor in which a cladding tube is filled with a large number of fuel pellets and a plenum spring is interposed between the fuel pellets and an end plug. Regarding improvement of the spring part.
一般に、原子炉用核燃料要素としては、多数個
の燃料ペレツトを被覆管内に充填積層したものが
多く使用されている。 In general, a nuclear fuel element for a nuclear reactor is often used in which a large number of fuel pellets are filled and stacked in a cladding tube.
第１図は、上記従来の原子炉用核燃料要素の縦
断面図であつて、被覆管１内に多数個の燃料ペレ
ツト２が充填積層され、その被覆管１の両端にそ
れぞれ端栓３および４が装着されている。上記燃
料ペレツト２の頂端部と上部端栓３との間には核
分裂生成ガスを収容するプレナム５が形成されて
おり、そのプレナム５には、上記互いに積層され
た燃料ペレツト２を押圧しその移動を防止するた
めのプレナムスプリング６が配設されている。と
ころで、上記プレナムスプリング６と燃料ペレツ
ト２との間には、スプリングの燃料ペレツト２へ
の押圧面積を増すとともに均一荷重が加わるよう
にするため、燃料ペレツト押え板７が介装せしめ
られており、しかも上記燃料ペレツト押え板７
は、その被覆管１内への挿入を容易にするため
に、あらかじめプレナムスプリング６の一端に溶
接接合されている。 FIG. 1 is a longitudinal sectional view of the conventional nuclear fuel element for a nuclear reactor, in which a large number of fuel pellets 2 are filled and stacked in a cladding tube 1, and end plugs 3 and 4 are provided at both ends of the cladding tube 1, respectively. is installed. A plenum 5 is formed between the top end of the fuel pellet 2 and the upper end plug 3 to accommodate the fission product gas, and the plenum 5 presses the stacked fuel pellets 2 to prevent their movement. A plenum spring 6 is provided to prevent this. Incidentally, a fuel pellet holding plate 7 is interposed between the plenum spring 6 and the fuel pellet 2 in order to increase the pressing area of the spring against the fuel pellet 2 and to apply a uniform load. Moreover, the fuel pellet holding plate 7
is welded to one end of the plenum spring 6 in advance to facilitate its insertion into the cladding tube 1.
したがつて、上述の如き従来の原子炉用核燃料
要素は、その製造に際してあらかじめプレナムス
プリングに対して燃料ペレツト押え板を溶接する
必要があり、そのため特別の溶接設備や治工具類
などの設備が必要であり、その設備費や溶接電極
などの消耗品費用がかかる等の問題がある。 Therefore, when manufacturing conventional nuclear fuel elements for nuclear reactors as described above, it is necessary to weld the fuel pellet holding plate to the plenum spring in advance, which requires special welding equipment, jigs, and other equipment. However, there are problems such as the cost of equipment and consumables such as welding electrodes.
本考案はこのような点に鑑み、プレナムスプリ
ングに対する溶接作業等を必要とせず、製造コス
トの低減を計り得るようにした原子炉用核燃料要
素を得ることを目的とするものであつて、従来の
燃料ペレツト押え板の代りに、プレナムスプリン
グの燃料ペレツト側端部に、燃料ペレツトの端面
に接触する渦巻き部を形成したことを特徴とする
ものである。 In view of these points, the present invention aims to obtain a nuclear fuel element for a nuclear reactor that does not require welding work for plenum springs and can reduce manufacturing costs. Instead of the fuel pellet presser plate, the plenum spring is characterized by forming a spiral portion on the fuel pellet side end portion to contact the end surface of the fuel pellet.
以下、第２図および第３図を参照して本考案を
その一実施例について説明する。なお、第１図と
同一部分には同一符号を付す。 Hereinafter, one embodiment of the present invention will be described with reference to FIGS. 2 and 3. Note that the same parts as in FIG. 1 are given the same reference numerals.
第２図において、被覆管１の両端にはそれぞれ
端栓３および４が装着され、その被覆管１内には
多数個の燃料ペレツト２が充填積層されており、
さらに上記燃料ペレツト２の頂部と上部端栓３と
の間にはプレナムスプリング６が介装されてい
る。この構成は従来のものと全く同一であるが、
本考案においては、上記プレナムスプリング６の
燃料ペレツトと当接する面側に、第３図に示すよ
うに、燃料ペレツトの端面に接触して燃料ペレツ
トを押圧する渦巻き部８が一体的に形成されてい
る。すなわち、上記プレナムスプリング６は、線
材の一端をまず線材が密着するようにして渦巻き
状に巻き、所定の寸法になつたところで渦巻き部
分に直角方向にら線状にスプリング部分を巻いて
いくことによつて形成されており、さらに燃料ペ
レツトとの当接面をグラインダー等により研削す
ることにより、平らな面でペレツトを押圧し得る
ようにしてある。 In FIG. 2, end plugs 3 and 4 are attached to both ends of a cladding tube 1, and a large number of fuel pellets 2 are filled and stacked inside the cladding tube 1.
Furthermore, a plenum spring 6 is interposed between the top of the fuel pellet 2 and the upper end plug 3. This configuration is exactly the same as the conventional one, but
In the present invention, as shown in FIG. 3, a spiral portion 8 is integrally formed on the side of the surface of the plenum spring 6 that contacts the fuel pellet, which contacts the end surface of the fuel pellet and presses the fuel pellet. There is. That is, the above-mentioned plenum spring 6 is made by first winding one end of the wire in a spiral shape so that the wire is in close contact with each other, and when the wire reaches a predetermined dimension, the spring portion is wound in a spiral shape in a direction perpendicular to the spiral portion. The surface that contacts the fuel pellets is ground with a grinder or the like so that the pellets can be pressed against the flat surface.
このように本考案においては、プレナムスプリ
ングの一端に上記プレナムスプリングと一体的に
渦巻き部が形成され、この渦巻き部によつてペレ
ツト押さえが構成されているので、従来のように
別体のペレツト押え板をプレナムスプリングに溶
着する必要がなく、特別な溶接装置等を必要とす
ることもなく、また溶接作業も行なわなくてよい
ので、その製造がきわめて簡単であり、製造コス
トを大幅に削減することができる。 In this way, in the present invention, a spiral portion is formed integrally with the plenum spring at one end of the plenum spring, and this spiral portion constitutes a pellet holder. There is no need to weld the plate to the plenum spring, no special welding equipment is required, and no welding work is required, so manufacturing is extremely simple and manufacturing costs can be significantly reduced. I can do it.
第１図は従来の原子炉用燃料要素の縦断面図、
第２図は本考案の原子炉用燃料要素の縦断面図、
第３図は本考案におけるプレナムスプリングの斜
視図である。
１……被覆管、２……燃料ペレツト、３，４…
…端栓、５……プレナム、６……プレナムスプリ
ング、８……渦巻き部。
Figure 1 is a vertical cross-sectional view of a conventional nuclear reactor fuel element.
Figure 2 is a longitudinal cross-sectional view of the nuclear reactor fuel element of the present invention;
FIG. 3 is a perspective view of the plenum spring in the present invention. 1...Claying tube, 2...Fuel pellets, 3, 4...
... End plug, 5 ... Plenum, 6 ... Plenum spring, 8 ... Spiral section.
Claims (1)
の燃料ペレツトと端栓との間にプレナムスプリン
グを介装した原子炉用核燃料要素において、上記
プレナムスプリングの燃料ペレツト側端部に、燃
料ペレツトの端面に接触する渦巻き部を形成した
ことを特徴とする、原子炉用核燃料要素。 In a nuclear fuel element for a nuclear reactor in which a cladding tube is filled with a large number of fuel pellets and a plenum spring is interposed between the fuel pellets and an end plug, the end face of the fuel pellet is attached to the end of the plenum spring on the fuel pellet side. A nuclear fuel element for a nuclear reactor, characterized in that a spiral portion is formed in contact with the vortex.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1983100294U JPS608894U (en) | 1983-06-29 | 1983-06-29 | Nuclear fuel elements for nuclear reactors |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1983100294U JPS608894U (en) | 1983-06-29 | 1983-06-29 | Nuclear fuel elements for nuclear reactors |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS608894U JPS608894U (en) | 1985-01-22 |
| JPS6326797Y2 true JPS6326797Y2 (en) | 1988-07-20 |
Family
ID=30237318
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1983100294U Granted JPS608894U (en) | 1983-06-29 | 1983-06-29 | Nuclear fuel elements for nuclear reactors |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS608894U (en) |
-
1983
- 1983-06-29 JP JP1983100294U patent/JPS608894U/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS608894U (en) | 1985-01-22 |
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