JPH0376873B2 - - Google Patents
Info
- Publication number
- JPH0376873B2 JPH0376873B2 JP60239890A JP23989085A JPH0376873B2 JP H0376873 B2 JPH0376873 B2 JP H0376873B2 JP 60239890 A JP60239890 A JP 60239890A JP 23989085 A JP23989085 A JP 23989085A JP H0376873 B2 JPH0376873 B2 JP H0376873B2
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel rod
- cladding tube
- protrusion
- elastic member
- 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 - Lifetime
Links
- 239000003758 nuclear fuel Substances 0.000 claims description 43
- 238000005253 cladding Methods 0.000 claims description 26
- 230000002093 peripheral effect Effects 0.000 claims description 9
- 239000000446 fuel Substances 0.000 description 5
- 238000003780 insertion Methods 0.000 description 5
- 230000037431 insertion Effects 0.000 description 5
- 238000000034 method Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000000956 alloy Substances 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 238000005452 bending Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion 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
Description
【発明の詳細な説明】
「産業上の利用分野」
この発明は、支持格子に固定する際に、被覆管
外周面に傷が発生するのを防止することができる
核燃料棒に関するものである。DETAILED DESCRIPTION OF THE INVENTION "Industrial Application Field" The present invention relates to a nuclear fuel rod that can prevent damage to the outer circumferential surface of a cladding tube when it is fixed to a support grid.
「従来の技術」
一般に、原子炉に装荷されている燃料集合体１
は、第１５図ないし第１７図に示されるように構
成されている。"Prior art" Generally, a fuel assembly 1 loaded in a nuclear reactor
is constructed as shown in FIGS. 15 to 17.
すなわち、この燃料集合体１は、第１５図にお
いて図中上下に離間して平行に配設された上部ノ
ズル１１および下部ノズル１２と、これらの間に
所定の間隔をおいて配設された複数の支持格子１
３と、第１６図に示されるようにこれら支持格子
１３に形成された多数の格子空間１４のうちの所
定の格子空間１５を挿通して前記上部ノズル１１
および下部ノズル１２にそれぞれの上下端部が連
結されて燃料集合体の骨組みを構成する制御棒案
内管１６と、前記支持格子１３の所定の格子空間
１７内に挿通された複数の核燃料棒１８とから構
成されている。 That is, as shown in FIG. 15, this fuel assembly 1 includes an upper nozzle 11 and a lower nozzle 12 arranged vertically apart and parallel to each other, and a plurality of nozzles arranged at a predetermined interval between them. support grid 1
3, and as shown in FIG.
and a control rod guide tube 16 whose upper and lower ends are connected to the lower nozzle 12 to constitute the framework of the fuel assembly, and a plurality of nuclear fuel rods 18 inserted into predetermined lattice spaces 17 of the support lattice 13. It consists of
ところで、このような燃料集合体１において、
核燃料棒１８を支持格子１３に固定するには、従
来、第１７図に示すような方法が採られている。
すなわち、所定の格子空間１７において、支持格
子１３を構成する合金製ストラツプ１９，１９に
は、前記所定の格子空間１７側に突出するスプリ
ング２０，２０が前記ストラツプの一部を変形さ
せて設けられている。また、このスプリング２
０，２０と対向するストラツプ１９，１９には前
記所定の空間１７側に突出するデインプル２１，
２１が同じく前記ストラツプの一部を変形させて
設けられている。そして、前記核燃料棒１８を、
前記所定の格子空間１７に挿入し、前記スプリン
グ２０，２０の弾性によつて前記デインプル２
１，２１に押圧して固定するようにしている。 By the way, in such a fuel assembly 1,
Conventionally, a method as shown in FIG. 17 has been used to fix the nuclear fuel rods 18 to the support grid 13.
That is, in a predetermined lattice space 17, the alloy straps 19, 19 constituting the support lattice 13 are provided with springs 20, 20 that protrude toward the predetermined lattice space 17 by partially deforming the straps. ing. Also, this spring 2
The straps 19, 19 facing the straps 0, 20 have dimples 21, which protrude toward the predetermined space 17,
21 is also provided by partially deforming the strap. Then, the nuclear fuel rod 18 is
The dimple 2 is inserted into the predetermined lattice space 17, and the dimple 2 is
1 and 21 to fix it.
「発明が解決しようとする問題点」
ところで、上記のような核燃料棒１８の固定方
法にあつては、核燃料棒を支持格子１３に装填す
る際、前記核燃料棒１８は前記スプリング２０お
よびデインプル２１によつて押圧された状態で挿
入されるため、前記スプリング２０およびデイン
プル２１によつて被覆管の外周面にキズがついて
しまう。このようなキズの発生は、原子炉内環境
下での被覆管腐食の発生点となつたり、核燃料棒
の曲がりを惹起する等、核燃料棒にとつて極力避
けることが望ましい。また、核燃料棒１８は、前
記スプリング２０によつてデインプル２１に圧接
された状態で挿入され、しかも支持格子１３は、
上下ノズル１１，１２間に何箇所か設けられてい
るため、挿入時の擢動抵抗はかなり大きい。この
ため核燃料棒１８に不必要な負荷が加わるという
問題点があつた。"Problems to be Solved by the Invention" By the way, in the method of fixing the nuclear fuel rods 18 as described above, when loading the nuclear fuel rods into the support grid 13, the nuclear fuel rods 18 are attached to the springs 20 and the dimples 21. Since the cladding tube is inserted in a pressed state, the outer peripheral surface of the cladding tube is scratched by the spring 20 and the dimple 21. It is desirable to avoid such scratches as much as possible for nuclear fuel rods, as they can become a point of occurrence for corrosion of the cladding tube in the environment inside the nuclear reactor, or cause bending of the nuclear fuel rods. Further, the nuclear fuel rod 18 is inserted while being pressed against the dimple 21 by the spring 20, and the support grid 13 is
Since the nozzles are provided at several locations between the upper and lower nozzles 11 and 12, the sliding resistance during insertion is quite large. Therefore, there was a problem in that an unnecessary load was applied to the nuclear fuel rods 18.
「発明の目的」
この発明は、支持格子に挿入および固定する際
に、被覆管外周面にキズがつくことを防止できる
とともに、挿入時の擢動抵抗のない核燃料棒を提
供することを目的とする。``Object of the Invention'' The object of the present invention is to provide a nuclear fuel rod that can prevent scratches on the outer circumferential surface of the cladding tube when inserted and fixed into a support grid, and that has no sliding resistance during insertion. do.
「発明の構成」
この発明は、被覆管の外周面に、半径方向に弾
性変形可能な弾性部材を、被覆管の外周面から半
径方向へ突出させて設けた構成としたものであ
る。[Structure of the Invention] The present invention has a structure in which an elastic member that can be elastically deformed in the radial direction is provided on the outer peripheral surface of the cladding tube so as to protrude in the radial direction from the outer peripheral surface of the cladding tube.
「実施例」
以下、この発明の実施例について第１図ないし
第１４図を参照して説明する。なお、これらの図
において、従来例と同一構成の部分には同一符号
を付して、その説明を省略する。"Embodiments" Hereinafter, embodiments of the present invention will be described with reference to FIGS. 1 to 14. In addition, in these figures, the same reference numerals are given to the parts having the same configuration as those of the conventional example, and the explanation thereof will be omitted.
第１図および第２図は、この発明に係る核燃料
棒３を示す図である。この核燃料棒３は、被覆管
３１の支持格子１３に支持される位置に円筒状の
円筒部材３２が嵌合されている。この円筒部材３
２は、その両端を固定リング３３，３３によつて
前記被覆管３１に固定されており、その両端部外
周面には弾性部材３４が嵌合して固定されてい
る。この弾性部材３４は、略環状をなす弾性体か
らなるものであつて、半径方向外方へ突出した突
出部３４ａが、周方向に４箇所等間隔に離間して
形成されている。この突出部３４ａは、半径方向
外方に向つて押圧する弾性を有しており、支持格
子１３のストラツプ１９を押圧することによつ
て、核燃料棒３を支持するようになつている。ま
たこの突出部３４ａの突出量は、前記所定の格子
空間１７内において、突出部３４ａの突出方向が
前記ストラツプ１９の交差部に向いて配設されて
いる場合には、ストラツプ１９に当接することが
なく、突出部３４ａの突出方向が前記ストラツプ
１９に垂直に配設されている場合には、前記スト
ラツプ１９に当接し半径方向内方へ圧縮されるよ
うに設定されており、核燃料棒３を挿入する際に
は前記突出部３４ａがストラツプ１９に接触しな
いように挿入し、挿入後核燃料棒３を回動させて
突出部３４ａをストラツプ１９に押圧して核燃料
棒３を固定できるようになつている。 FIG. 1 and FIG. 2 are diagrams showing a nuclear fuel rod 3 according to the present invention. In this nuclear fuel rod 3, a cylindrical member 32 is fitted into a cylindrical member 32 at a position supported by the support grid 13 of the cladding tube 31. This cylindrical member 3
2 is fixed to the cladding tube 31 at both ends by fixing rings 33, 33, and an elastic member 34 is fitted and fixed to the outer circumferential surface of both ends. The elastic member 34 is made of a substantially annular elastic body, and has four protrusions 34a that protrude outward in the radial direction and are equally spaced apart in the circumferential direction. This protrusion 34a has elasticity to press outward in the radial direction, and supports the nuclear fuel rod 3 by pressing the strap 19 of the support grid 13. Further, the amount of protrusion of the protrusion 34a is such that if the protrusion direction of the protrusion 34a is disposed within the predetermined lattice space 17 so as to face the intersection of the straps 19, the protrusion 34a may come into contact with the strap 19. If the protrusion 34a is arranged perpendicularly to the strap 19, the protrusion 34a is set to come into contact with the strap 19 and be compressed radially inward, thereby causing the nuclear fuel rod 3 to When inserting, the nuclear fuel rod 3 is inserted so that the protrusion 34a does not come into contact with the strap 19, and after insertion, the nuclear fuel rod 3 is rotated and the protrusion 34a is pressed against the strap 19, so that the nuclear fuel rod 3 can be fixed. There is.
なお、所定の格子空間１７を画成するストラツ
プ１９には、第３図に示すように、ストラツプ同
士の交差部から当距離の位置に、係合部４１が形
成されている。この係合部４１は、前記所定の格
子空間１７側へ突出した２つの凸部４１ａ，４１
ａからなつており、前記突出部３４ａに係合して
前記核燃料棒３が周方向に回動しないようになつ
ている。 Incidentally, as shown in FIG. 3, an engaging portion 41 is formed on the strap 19 defining the predetermined grid space 17 at a position the same distance from the intersection of the straps. This engaging portion 41 includes two convex portions 41a and 41 that protrude toward the predetermined grid space 17.
a, which engages with the protrusion 34a to prevent the nuclear fuel rod 3 from rotating in the circumferential direction.
このような核燃料棒３を支持格子１３に固定す
るには、まず核燃料棒３を、支持格子１３の所定
の格子空間１７の中心を通る軸線上に、突出部の
突出方向がストラツプ１９と45゜をなすように配
設する。次に、前記核燃料棒３を軸方向に移動さ
せ、支持格子１３の所定の格子空間１７内に挿入
する。この際、第４図に示すように、突出部３４
ａは、所定の格子空間１７の四隅の位置を通過す
るため、支持格子１３には接触しない。そして、
前記核燃料棒３を所定の位置まで挿入し、前記弾
性部材３４が所定の格子空間１７内に位置した
ら、前記核燃料棒３を周方向に45゜回転させる。
そして、第５図に示すように、前記突出部３４ａ
を、前記係合部４１の２つの凸部４１ａ，４１ａ
の間に係合させるとともに、半径方向内方に圧縮
させて核燃料棒３を固定する。 In order to fix such a nuclear fuel rod 3 to the support grid 13, first, the nuclear fuel rod 3 is placed on an axis passing through the center of a predetermined grid space 17 of the support grid 13, so that the protrusion direction of the protrusion is 45 degrees with respect to the strap 19. Arrange it so that it forms. Next, the nuclear fuel rod 3 is moved in the axial direction and inserted into a predetermined lattice space 17 of the support lattice 13. At this time, as shown in FIG.
Since point a passes through the four corners of the predetermined grid space 17, it does not contact the support grid 13. and,
When the nuclear fuel rod 3 is inserted to a predetermined position and the elastic member 34 is positioned within the predetermined lattice space 17, the nuclear fuel rod 3 is rotated by 45 degrees in the circumferential direction.
Then, as shown in FIG. 5, the protrusion 34a
, the two convex portions 41a, 41a of the engaging portion 41
The nuclear fuel rods 3 are fixed by being engaged between them and being compressed radially inward.
上記のように、この核燃料棒３にあつては、被
覆管３１の外周に突出部３４ａを有する弾性部材
３４を設け、支持格子１３側に被覆管の外周面を
押圧する部材を設けていないから、核燃料棒３を
支持格子１３に挿入する際に、被覆管３１の外周
面を傷付けることがなく、さらに挿入時の擢動抵
抗をなくすことができる。 As mentioned above, in this nuclear fuel rod 3, the elastic member 34 having the protrusion 34a is provided on the outer periphery of the cladding tube 31, and no member for pressing the outer peripheral surface of the cladding tube is provided on the support grid 13 side. When the nuclear fuel rod 3 is inserted into the support grid 13, the outer circumferential surface of the cladding tube 31 is not damaged, and furthermore, the sliding resistance at the time of insertion can be eliminated.
次に、本発明の他の実施例について、第６図お
よび第７図を参照して説明する。この実施例にお
いても前記核燃料棒３と同様の作用効果を奏する
ことは勿論である。なお、これらの図において、
前記核燃料棒３と同一構成の部分には同一符号を
付して、その説明を省略する。 Next, another embodiment of the present invention will be described with reference to FIGS. 6 and 7. It goes without saying that this embodiment also has the same effects as the nuclear fuel rod 3 described above. In addition, in these figures,
Components having the same configuration as those of the nuclear fuel rod 3 are designated by the same reference numerals, and their explanations will be omitted.
この核燃料棒５は、被覆管３１に弾性部材５１
が嵌合されてなるものである。この弾性部材５１
は、両端に設けられた円筒部５１ａ，５１ａと、
この円筒部５１ａ，５１ａの間に橋渡され、半径
方向外方に張り出され、周方向に４箇所等間隔に
離間して設けられた突出部５１ｂ，５１ｂ，５１
ｂ，５１ｂとから構成されている。この突出部５
１ｂは、前記弾性部材３４の突出部３４ａと同様
に、半径方向外方に向つて押圧する弾性を有して
いるとともに、その突出量も前記突出部３４ａと
同様に設定されている。 This nuclear fuel rod 5 has an elastic member 51 in the cladding tube 31.
are fitted together. This elastic member 51
has cylindrical parts 51a, 51a provided at both ends,
Projecting portions 51b, 51b, 51 are bridged between the cylindrical portions 51a, 51a, project outward in the radial direction, and are provided at four equally spaced locations in the circumferential direction.
b, 51b. This protrusion 5
Like the protrusion 34a of the elastic member 34, the protrusion 1b has elasticity to press outward in the radial direction, and its protrusion amount is set similarly to the protrusion 34a.
なお、上記実施例においては、円筒部材３２、
弾性部材５１は、固定リング３３によつて被覆管
３１に固定されているが、これに限る必要はな
く、第８図および第９図、第１０図および第１１
図にそれぞれ示す核燃料棒６，７のように固定し
てもよい。すなわち、第１２図に示すように、被
覆管６１にフランジ部６１ａ，６１ｂを設け、こ
れによつて前記円筒部材３２、弾性部材５１の両
端を固定するようにしてもよい。この場合、円筒
部材３２、弾性部材５１は、それぞれ第１３図お
よび第１４図に示すように、その円筒面が軸方向
に切り開かれたものを用意し、これを前記被覆管
６１のフランジ部６１ａとフランジ部６１ｂとの
間の外周面に巻き付け、切り開かれた端縁Ｗを第
８図ないし第１１図に示すように溶接して固定す
る。 In addition, in the above embodiment, the cylindrical member 32,
The elastic member 51 is fixed to the cladding tube 31 by the fixing ring 33, but it is not limited to this, and the elastic member 51 is fixed to the cladding tube 31 by the fixing ring 33.
They may also be fixed like nuclear fuel rods 6 and 7 shown in the figure, respectively. That is, as shown in FIG. 12, the cladding tube 61 may be provided with flanges 61a and 61b, thereby fixing both ends of the cylindrical member 32 and the elastic member 51. In this case, the cylindrical member 32 and the elastic member 51 have their cylindrical surfaces cut in the axial direction, as shown in FIGS. 13 and 14, respectively. and the flange portion 61b, and the cut edge W is welded and fixed as shown in FIGS. 8 to 11.
「発明の効果」
以上に説明したように、この発明によれば、被
覆管の外周面に、半径方向に弾性変形可能な弾性
部材を、被覆管の外周面から半径方向へ突出させ
て設けているから、核燃料棒を支持格子に挿入お
よび固定する際に、被覆管外周面にキズがつくこ
とを防止できるとともに、挿入時の擢動抵抗を全
くなくすることができるという効果がえられる。"Effects of the Invention" As explained above, according to the present invention, an elastic member that can be elastically deformed in the radial direction is provided on the outer peripheral surface of the cladding tube so as to protrude in the radial direction from the outer peripheral surface of the cladding tube. Therefore, when inserting and fixing the nuclear fuel rod into the support grid, it is possible to prevent the outer peripheral surface of the cladding tube from being scratched, and it is possible to completely eliminate the sliding resistance during insertion.
第１図および第２図はこの発明の一実施例であ
る核燃料棒を示す図であつて、第１図はその正面
図、第２図は第１図中−線視断面図、第３図
は核燃料棒を固定する所定の格子空間を示す平面
図、第４図および第５図は所定の格子空間に核燃
料棒を固定する方法を示す平面図、第６図および
第７図はこの発明の他の実施例である核燃料棒を
示す図であつて、第６図はその正面図、第７図は
第６図中−線視断面図、第８図および第９図
は被覆管に設けられたフランジ部に円筒部材を固
定した核燃料棒を示すものであつて、第８図はそ
の正面図、第９図は第８図中−線視断面図、
第１０図および第１１図は被覆管に設けられたフ
ランジ部に弾性部材を固定した核燃料棒を示すも
のであつて、第１０図はその正面図、第１１図は
第１０図中XI−XI線視断面図、第１２図はフラン
ジ部を有する被覆管を示す正面図、第１３図は切
り開かれた円筒部材を示す正面図、第１４図は切
り開かれた弾性部材を示す正面図、第１５図は燃
料集合体を示す一部切欠き正面図、第１６図は第
１５図中−線視断面図、第１７図は第１
６図中矢印部分の拡大断面図である。
３……核燃料棒、５……核燃料棒、６……核燃
料棒、７……核燃料棒、３１……被覆管、３４…
…弾性部材、５１……弾性部材、６１……被覆
管。
1 and 2 are diagrams showing a nuclear fuel rod that is an embodiment of the present invention, in which FIG. 1 is a front view thereof, FIG. 2 is a sectional view taken along the line in FIG. 1, and FIG. is a plan view showing a predetermined lattice space for fixing nuclear fuel rods, FIGS. 4 and 5 are plan views showing a method for fixing nuclear fuel rods in a predetermined lattice space, and FIGS. 6 is a front view thereof, FIG. 7 is a cross-sectional view taken along the line in FIG. 6, and FIGS. 8 and 9 are views showing a nuclear fuel rod as another embodiment. 8 is a front view thereof, FIG. 9 is a sectional view taken along the line in FIG. 8, and FIG.
10 and 11 show a nuclear fuel rod in which an elastic member is fixed to a flange portion provided on a cladding tube, FIG. 10 is a front view thereof, and FIG. 12 is a front view showing a cladding tube having a flange portion, FIG. 13 is a front view showing a cut-out cylindrical member, FIG. 14 is a front view showing a cut-out elastic member, and FIG. 15 is a front view showing a cladding tube having a flange portion. The figure is a partially cutaway front view showing the fuel assembly, FIG. 16 is a sectional view taken along the line in FIG. 15, and FIG.
6 is an enlarged sectional view of the arrowed portion in FIG. 6. FIG. 3... Nuclear fuel rod, 5... Nuclear fuel rod, 6... Nuclear fuel rod, 7... Nuclear fuel rod, 31... Cladding tube, 34...
... Elastic member, 51 ... Elastic member, 61 ... Cladding tube.
Claims (1)
な弾性部材を、被覆管の外周面から半径方向へ突
出させて設けたことを特徴とする核燃料棒。1. A nuclear fuel rod characterized in that an elastic member that can be elastically deformed in the radial direction is provided on the outer peripheral surface of the cladding tube so as to protrude in the radial direction from the outer peripheral surface of the cladding tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60239890A JPS62100692A (en) | 1985-10-26 | 1985-10-26 | Nuclear fuel rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60239890A JPS62100692A (en) | 1985-10-26 | 1985-10-26 | Nuclear fuel rod |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62100692A JPS62100692A (en) | 1987-05-11 |
| JPH0376873B2 true JPH0376873B2 (en) | 1991-12-06 |
Family
ID=17051388
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60239890A Granted JPS62100692A (en) | 1985-10-26 | 1985-10-26 | Nuclear fuel rod |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62100692A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8853314B2 (en) | 2008-10-23 | 2014-10-07 | Datalase Ltd. | Heat absorbing additives |
| US9267042B2 (en) | 2008-10-27 | 2016-02-23 | Datalase Ltd. | Coating composition for marking substrates |
| US9333786B2 (en) | 2007-07-18 | 2016-05-10 | Datalase, Ltd. | Laser-sensitive coating formulations |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4800061A (en) * | 1987-05-06 | 1989-01-24 | Westinghouse Electric Corp. | Apparatus for loading fuel rods into grids of nuclear fuel assemblies |
| US5386444A (en) * | 1993-01-15 | 1995-01-31 | General Electric Company | Fuel rod loading apparatus |
-
1985
- 1985-10-26 JP JP60239890A patent/JPS62100692A/en active Granted
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9333786B2 (en) | 2007-07-18 | 2016-05-10 | Datalase, Ltd. | Laser-sensitive coating formulations |
| US8853314B2 (en) | 2008-10-23 | 2014-10-07 | Datalase Ltd. | Heat absorbing additives |
| US9267042B2 (en) | 2008-10-27 | 2016-02-23 | Datalase Ltd. | Coating composition for marking substrates |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS62100692A (en) | 1987-05-11 |
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