JPH02163694A - Fuel rod for fast breeder - Google Patents
Fuel rod for fast breederInfo
- Publication number
- JPH02163694A JPH02163694A JP63320145A JP32014588A JPH02163694A JP H02163694 A JPH02163694 A JP H02163694A JP 63320145 A JP63320145 A JP 63320145A JP 32014588 A JP32014588 A JP 32014588A JP H02163694 A JPH02163694 A JP H02163694A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- fuel rod
- fuel rods
- pipe
- ribs
- 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 title claims abstract description 46
- 238000005253 cladding Methods 0.000 claims abstract description 17
- 239000003758 nuclear fuel Substances 0.000 claims description 2
- 239000002826 coolant Substances 0.000 abstract description 5
- 239000008188 pellet Substances 0.000 abstract description 4
- 229910052770 Uranium Inorganic materials 0.000 abstract description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract description 3
- 229910052778 Plutonium Inorganic materials 0.000 abstract description 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 abstract description 2
- 238000005245 sintering Methods 0.000 abstract 1
- 125000006850 spacer group Chemical group 0.000 description 12
- 238000004804 winding Methods 0.000 description 4
- 238000003780 insertion Methods 0.000 description 2
- 230000037431 insertion Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 101100334009 Caenorhabditis elegans rib-2 gene Proteins 0.000 description 1
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical compound C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000000717 retained effect 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
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は高速増殖炉用燃料棒に係り、特に燃料集合体を
構成した場合に各燃料棒の間隔を確実に保持し得るよう
にした高速増殖炉用燃料棒に関す（従来の技術）
第３図は高速増殖炉用燃料棒集合体の概略構造を示す縦
断面図であり、多数本の燃料棒１が断面六角形状になる
ように支持プレート２に組み立てられ、その燃料棒１の
束が断面六角形状のラッパ管３内に挿入され、その一端
にエントランスノズル４を嵌合溶着するとともに、他端
にハンドリングヘッド５が嵌合溶着されている。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to fuel rods for fast breeder reactors, and in particular, to a method for reliably maintaining the spacing between each fuel rod when forming a fuel assembly. Related to fuel rods for fast breeder reactors (prior art) Fig. 3 is a longitudinal sectional view showing the schematic structure of a fuel rod assembly for fast breeder reactors, in which a large number of fuel rods 1 have a hexagonal cross section. The bundle of fuel rods 1 is inserted into a wrapper tube 3 having a hexagonal cross section, and an entrance nozzle 4 is fitted and welded to one end of the tube, and a handling head 5 is attached to the other end. Fitted and welded.
ところで、上記燃料集合体を構成する各燃料棒］は、第
４図に示すように、薄肉円筒状の被覆管６内に、ウラン
又はブルトニウムの酸化物を焼結した複数の燃料ベレッ
ト７を装填し、その両端を上部端栓８および下部端栓９
によって密封するとともに、内部に不活性ガスが充填さ
れている。そして、上記被覆管６の外面にスペーサワイ
ヤ１−０か螺旋状の巻付は溶る“固定され、そのスペー
サワイヤ１０によって第５図に示すように隣接燃料棒と
の間に所定間隙が形成され、所定面積の冷却材流路か形
成されるようにしである。By the way, as shown in FIG. 4, each fuel rod constituting the above-mentioned fuel assembly consists of a thin-walled cylindrical cladding tube 6 loaded with a plurality of fuel pellets 7 made of sintered oxides of uranium or brutonium. and connect both ends to an upper end plug 8 and a lower end plug 9.
The inside is sealed with an inert gas. Then, the spacer wire 1-0 spirally wrapped around the outer surface of the cladding tube 6 is melted and fixed, and the spacer wire 10 forms a predetermined gap between adjacent fuel rods as shown in FIG. This is done so that a coolant flow path of a predetermined area is formed.
（発明が解決しようとする課題）
ところが、このようなものにおいては被覆管６の外面に
巻装するスペーサワイヤ１０に所要の張力又はピッチが
得られなかったり、局所歪やねじれ、傷等が発生し、仕
様を満足できないケースか生じたり、後工程のスペーサ
ワイヤ型燃料結束後のラッパ管への挿入ができなかった
り、或はその挿入に支障をきたすケースが発生ずる等の
問題がある。まして、プルトニウム燃料等の取扱いに際
しては、放射線防護上、全自動化設備となり、設備が大
型化し、コストが膨大となる恐れがある。(Problems to be Solved by the Invention) However, in such a device, the required tension or pitch may not be obtained in the spacer wire 10 wound around the outer surface of the cladding tube 6, or local distortion, twisting, flaws, etc. may occur. However, there are problems such as cases in which the specifications cannot be satisfied, cases in which insertion into the wrapper tube after spacer wire type fuel bundling in the subsequent process is impossible, or cases in which the insertion is hindered. Furthermore, when handling plutonium fuel, etc., the equipment must be fully automated for radiation protection reasons, which may increase the size and cost of the equipment.
本発明はこのような点に鑑み、従来のスペーサワイヤ型
の燃料と同等の性能を有し、スペーサワイヤの巻き付は
溶着、固定等の製造工程を省略し得る高速増殖炉用燃料
棒を得ることを目的とする。In view of these points, the present invention provides a fuel rod for a fast breeder reactor that has performance equivalent to that of conventional spacer wire type fuel and that can omit manufacturing steps such as welding and fixing the winding of the spacer wire. The purpose is to
（課題を解決するための手段）
本発明は、内部に核燃料を装填した薄肉円筒状の被覆管
の外表面に螺旋状リブを一体的に形成したことを特徴と
するものである。(Means for Solving the Problems) The present invention is characterized in that a spiral rib is integrally formed on the outer surface of a thin-walled cylindrical cladding tube in which nuclear fuel is loaded.
（作 用）
燃料集合体の組立に際し、燃料棒の被覆管の外表面に設
けられている螺旋状リブが隣接する燃料棒の外面に当接
し、上記リブによって各燃料棒の間隔が所定値に保持さ
れる。しかもこの場合、」１記螺旋状のリブは被覆管自
体に一体的に形成されているので、特にワイヤ巻（＝１
作業等を必要とせず、また張力、ピッチ、局所歪等の品
質上の問題か生じることがない。(Function) When assembling a fuel assembly, the spiral ribs provided on the outer surface of the fuel rod cladding tube come into contact with the outer surfaces of adjacent fuel rods, and the ribs maintain the spacing between each fuel rod at a predetermined value. Retained. Furthermore, in this case, since the spiral ribs mentioned in item 1 are integrally formed on the cladding tube itself, the wire winding (=1
No work is required, and there are no quality problems such as tension, pitch, or local distortion.
（実施例）
以下、第１図および第２図を参照して本発明の一実施例
について説明する。(Example) Hereinafter, an example of the present invention will be described with reference to FIGS. 1 and 2.
第１図は本発明の燃料棒の斜視図であって、薄肉円筒状
の被覆管６内にはウラン又はプルトニウムの酸化物を焼
結した複数の燃料ベレット７が装填され、その両端に上
部端栓８および下部端栓９が装イクされている。FIG. 1 is a perspective view of the fuel rod of the present invention, in which a plurality of fuel pellets 7 made of sintered uranium or plutonium oxide are loaded into a thin-walled cylindrical cladding tube 6, with an upper end at both ends. A plug 8 and a lower end plug 9 are loaded.
ところで、上記被覆管６の外表面には、螺旋状のリブ２
０が被覆管６の全長にわたり所定のピッチおよび巻数で
一体的に形成されている。By the way, the outer surface of the cladding tube 6 has a spiral rib 2.
0 are integrally formed over the entire length of the cladding tube 6 at a predetermined pitch and number of turns.
しかして、燃料集合体として組立てた場合上記螺旋状リ
ブ２０が隣接する燃料棒の被覆管６の外表面に当接し、
隣接する燃料棒間の間隔が正確に保持され、正確に冷却
材流路が形成される。しかも、この燃料棒の製造に際し
ては、螺旋状リブ付被覆管６に下部端栓９を溶着し、そ
の被覆管６内に燃料ベレット７を装填し、上部端栓８を
溶着密封するのみてよく、従来のようにスペーサワイヤ
を巻装し、溶着固定する必要がなく、そのための特別の
設備も必要としない。さらに、スペーサワイヤの巻装時
に生じるようなピッチずれ、ゆるみ等はなく、燃料集合
体組立時にラッパ管の装着が困難になるようなことがな
い。Therefore, when assembled as a fuel assembly, the spiral rib 20 contacts the outer surface of the cladding tube 6 of the adjacent fuel rod,
The spacing between adjacent fuel rods is maintained accurately and coolant flow paths are accurately formed. Furthermore, when manufacturing this fuel rod, it is only necessary to weld the lower end plug 9 to the spiral ribbed cladding tube 6, load the fuel pellet 7 into the cladding tube 6, and seal the upper end plug 8 by welding. There is no need to wind the spacer wire and weld and fix it as in the conventional method, and no special equipment is required for this purpose. Furthermore, there is no pitch deviation or loosening that occurs when winding spacer wires, and there is no difficulty in attaching the wrapper tube when assembling the fuel assembly.
第２図は上記燃料棒の断面図であり、螺旋状リブの断面
は正確な冷却材流路の確保及び適正な燃料棒間隔の保持
上、第２図（ａ）のように半円形状でもよく、第２図（
ｂ）のように台形形状または両者を併用した第２図（Ｃ
）に示すような形状としてもよい。Fig. 2 is a cross-sectional view of the fuel rod, and the cross section of the spiral rib may be semicircular as shown in Fig. 2(a) in order to ensure an accurate coolant flow path and maintain appropriate fuel rod spacing. Well, Figure 2 (
Figure 2 (C) shows trapezoidal shape or a combination of both as shown in b
) may be used.
以上説明したように、本発明においては薄肉円筒状の被
覆管の外表面に螺旋状リブを一体的に設けたので、その
螺旋状リブによって隣接燃料棒との間隔が所定値に保持
され、冷却材流通路が確実に確保される。しかも、従来
のスペーサワイヤ型の燃料棒のようにスペーサワイヤの
巻装、固着等の作業を行なう必要がなく、そのための設
備も必要とせず、本作業に係わる放射線被曝もなく安全
性を向上できる。さらに、スペーサワイヤを装着するも
ののようにスペーサであるリブにピ・ソチずれ、ゆるみ
′：９が生ずるようなことがなく、う・ソ／ぐ管の装着
に支障が生ずるようなこともない。As explained above, in the present invention, since the spiral ribs are integrally provided on the outer surface of the thin-walled cylindrical cladding tube, the distance between adjacent fuel rods is maintained at a predetermined value by the spiral ribs, and the cooling A material flow path is ensured. Moreover, unlike conventional spacer wire type fuel rods, there is no need to perform work such as winding and fixing spacer wires, no equipment is required, and there is no radiation exposure associated with this work, improving safety. . Furthermore, there is no possibility that the spacer ribs will be misaligned or loosened, unlike when a spacer wire is attached, and there will be no problem in attaching the pipe.
第１図は本発明の燃料棒の斜視図、第２図（ａ）（ｂ）
、 （Ｃ）はそれぞれ本発明の燃料棒の各実施例の断
面図、第３図は燃料集合体の縦断面図、第４図は従来の
燃料棒の斜視図、第５図は隣接する燃料棒間の状態を示
す拡大図である。
１・・・燃料棒、
６・・・被覆管、
７・・燃料ベレッ］・、
８・・・上部端栓、
９−・上部端栓、
２０・・螺旋状リブ。Figure 1 is a perspective view of the fuel rod of the present invention, Figures 2 (a) and (b)
, (C) is a cross-sectional view of each embodiment of the fuel rod of the present invention, FIG. 3 is a vertical cross-sectional view of a fuel assembly, FIG. 4 is a perspective view of a conventional fuel rod, and FIG. 5 is a cross-sectional view of an adjacent fuel rod. It is an enlarged view showing the state between the bars. DESCRIPTION OF SYMBOLS 1... Fuel rod, 6... Cladding tube, 7... Fuel bellet], 8... Upper end plug, 9-... Upper end plug, 20... Spiral rib.
Claims (1)
面に螺旋状リブを一体的に形成したことを特徴とする、
高速増殖炉用燃料棒。 ２、螺旋状リブの断面形状は半円又は台形形状であるこ
とを特徴とする、請求項１記載の高速増殖炉用燃料棒。[Claims] 1. A spiral rib is integrally formed on the outer surface of a thin-walled cylindrical cladding tube in which nuclear fuel is loaded,
Fuel rods for fast breeder reactors. 2. The fuel rod for a fast breeder reactor according to claim 1, wherein the spiral rib has a semicircular or trapezoidal cross-sectional shape.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63320145A JPH02163694A (en) | 1988-12-19 | 1988-12-19 | Fuel rod for fast breeder |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63320145A JPH02163694A (en) | 1988-12-19 | 1988-12-19 | Fuel rod for fast breeder |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH02163694A true JPH02163694A (en) | 1990-06-22 |
Family
ID=18118213
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63320145A Pending JPH02163694A (en) | 1988-12-19 | 1988-12-19 | Fuel rod for fast breeder |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH02163694A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2015076697A1 (en) | 2013-11-19 | 2015-05-28 | Открытое Акционерное Общество "Акмэ-Инжиниринг" | Fuel rod cladding, fuel rod and fuel assembly |
| RU2589010C2 (en) * | 2013-01-09 | 2016-07-10 | Потапов Юрий Васильевич | Fast neutron nuclear reactor fuel element |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5547666B2 (en) * | 1976-03-03 | 1980-12-01 | ||
| JPS6339913A (en) * | 1986-08-06 | 1988-02-20 | Nippon Polyurethan Kogyo Kk | Production of polyethylene vinyl ester polyurethane |
-
1988
- 1988-12-19 JP JP63320145A patent/JPH02163694A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5547666B2 (en) * | 1976-03-03 | 1980-12-01 | ||
| JPS6339913A (en) * | 1986-08-06 | 1988-02-20 | Nippon Polyurethan Kogyo Kk | Production of polyethylene vinyl ester polyurethane |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2589010C2 (en) * | 2013-01-09 | 2016-07-10 | Потапов Юрий Васильевич | Fast neutron nuclear reactor fuel element |
| WO2015076697A1 (en) | 2013-11-19 | 2015-05-28 | Открытое Акционерное Общество "Акмэ-Инжиниринг" | Fuel rod cladding, fuel rod and fuel assembly |
| JP2016537656A (en) * | 2013-11-19 | 2016-12-01 | ジョイント ストック カンパニー“アクメ−エンジニアリング” | Fuel rod cladding tube, fuel rod and fuel assembly |
| EP3076397A4 (en) * | 2013-11-19 | 2017-04-12 | Joint Stock Company "Akme-Engineering" | Fuel rod cladding, fuel rod and fuel assembly |
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