JPS6335951B2 - - Google Patents

Info

Publication number
JPS6335951B2
JPS6335951B2 JP58117946A JP11794683A JPS6335951B2 JP S6335951 B2 JPS6335951 B2 JP S6335951B2 JP 58117946 A JP58117946 A JP 58117946A JP 11794683 A JP11794683 A JP 11794683A JP S6335951 B2 JPS6335951 B2 JP S6335951B2
Authority
JP
Japan
Prior art keywords
fuel
plenum spring
pellet
plenum
nuclear
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
Application number
JP58117946A
Other languages
Japanese (ja)
Other versions
JPS608783A (en
Inventor
Kenzo Saito
Kojiro Komuro
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
NIPPON NUCLEAR FUELS
Original Assignee
NIPPON NUCLEAR FUELS
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by NIPPON NUCLEAR FUELS filed Critical NIPPON NUCLEAR FUELS
Priority to JP58117946A priority Critical patent/JPS608783A/en
Publication of JPS608783A publication Critical patent/JPS608783A/en
Publication of JPS6335951B2 publication Critical patent/JPS6335951B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Catalysts (AREA)

Description

【発明の詳細な説明】 本発明は、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. Furthermore, the fuel pellet presser plate is welded to one end of the plenum spring 6 in advance in order 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.

本発明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、プレナ
ムスプリングの燃料ペレツト側端部の密着巻部分
を形成し、その密着巻部分内にプレナムスプリン
グとともに燃料ペレツトに当接する少なくとも1
個のコイルを螺装したことを特徴とする。
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 etc. for the plenum spring and can reduce manufacturing costs. A tightly wound portion is formed at the end of the fuel pellet on the side of the fuel pellet, and within the tightly wound portion, there is at least one portion that contacts the fuel pellet together with a plenum spring.
It is characterized by having several coils screwed together.

以下、第2図乃至第4図を参照して本発明をそ
の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。
Embodiments of the present invention will be described below with reference to FIGS. 2 to 4. 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
燃料ペレツト側端部(下端部)に密着巻部分8が
形成されており、この密着巻部分8に、第3図に
示すように1個のコイル9、或は第4図に示すよ
うに2個のコイル9,10が同心状に螺装され、
上記コイル9,10の下端面がプレナムスプリン
グ6の下面と同一面内にあるようにしてある。
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, a tightly wound portion 8 is formed at the fuel pellet side end (lower end) of the plenum spring 6, and one coil 9, as shown in FIG. 3, is formed in this tightly wound portion 8. Alternatively, as shown in FIG. 4, two coils 9 and 10 are screwed concentrically,
The lower end surfaces of the coils 9 and 10 are arranged in the same plane as the lower surface of the plenum spring 6.

しかして、プレナムスプリング6の下面はその
下端に螺装されたコイル9等とともに燃料ペレツ
ト2に当接し、比較的広い面積で上記燃料ペレツ
ト2を押圧してその移動を防止する。
The lower surface of the plenum spring 6, together with the coil 9 etc. screwed onto its lower end, comes into contact with the fuel pellet 2, and presses the fuel pellet 2 over a relatively wide area to prevent its movement.

このように本発明においては、プレナムスプリ
ングの燃料ペレツト側端部に密着巻部分を形成
し、その密着巻部分に少なくとも1個のコイルを
螺装し、このコイルの端部およびプレナムスプリ
ングの端部によつて燃料ペレツトを押えるように
したので、従来のように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て、単にコイ
ルをねじ込むだけでよいのでその取付けがきわめ
て簡単であり、しかも特別な溶接装置等を必要と
することもなく、製造コストを大幅に低減するこ
とができる。
As described above, in the present invention, a tightly wound portion is formed at the end of the plenum spring on the fuel pellet side, at least one coil is screwed into the tightly wound portion, and the end of this coil and the end of the plenum spring are formed. Since the fuel pellets are held down by the plenum spring, there is no need to weld the pellet holding plate to the plenum spring as in the conventional case, and the installation is extremely simple as it is only necessary to screw the coil in. No equipment is required, and manufacturing costs can be significantly reduced.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は従来の原子炉用燃料要素の縦断面図、
第2図は本発明の原子炉用核燃料要素の縦断面
図、第3図はプレナムスプリングの燃料ペレツト
側端部の拡大断面図、第4図は本発明の他の実施
例を示す第3図と同一部分を示す拡大断面図であ
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……密着巻部分、9,10……コイル。
Figure 1 is a vertical cross-sectional view of a conventional nuclear reactor fuel element.
FIG. 2 is a longitudinal sectional view of a nuclear fuel element for a nuclear reactor according to the present invention, FIG. 3 is an enlarged sectional view of the end of a plenum spring on the fuel pellet side, and FIG. 4 is a third diagram showing another embodiment of the present invention. It is an enlarged sectional view showing the same part. 1...Claying tube, 2...Fuel pellets, 3, 4...
...End plug, 5...Plenum, 6...Plenum spring, 8...Tightly wound portion, 9, 10...Coil.

Claims (1)

【特許請求の範囲】[Claims] 1 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密
着巻部分を形成し、その密着巻部分内にプレナム
スプリングとともに燃料ペレツトに当接する少な
くとも1個のコイルを螺装したことを特徴とす
る、原子炉用核燃料要素。
1 Fill the cladding tube with a large number of fuel pellets,
In a nuclear fuel element for a nuclear reactor in which a plenum spring is interposed between the fuel pellet and the end plug, a tightly wound portion is formed at the end of the plenum spring on the fuel pellet side, and the fuel is inserted together with the plenum spring into the tightly wound portion. 1. A nuclear fuel element for a nuclear reactor, characterized in that at least one coil is threaded onto the pellet.
JP58117946A 1983-06-29 1983-06-29 Nuclear fuel element for nuclear reactor Granted JPS608783A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58117946A JPS608783A (en) 1983-06-29 1983-06-29 Nuclear fuel element for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58117946A JPS608783A (en) 1983-06-29 1983-06-29 Nuclear fuel element for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS608783A JPS608783A (en) 1985-01-17
JPS6335951B2 true JPS6335951B2 (en) 1988-07-18

Family

ID=14724139

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58117946A Granted JPS608783A (en) 1983-06-29 1983-06-29 Nuclear fuel element for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS608783A (en)

Also Published As

Publication number Publication date
JPS608783A (en) 1985-01-17

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