JPS6312549B2 - - Google Patents
Info
- Publication number
- JPS6312549B2 JPS6312549B2 JP56005989A JP598981A JPS6312549B2 JP S6312549 B2 JPS6312549 B2 JP S6312549B2 JP 56005989 A JP56005989 A JP 56005989A JP 598981 A JP598981 A JP 598981A JP S6312549 B2 JPS6312549 B2 JP S6312549B2
- Authority
- JP
- Japan
- Prior art keywords
- support
- nuclear fuel
- lattice
- corner
- support grid
- 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
- 239000003758 nuclear fuel Substances 0.000 claims description 22
- 239000000463 material Substances 0.000 claims description 3
- 229910045601 alloy Inorganic materials 0.000 claims description 2
- 239000000956 alloy Substances 0.000 claims description 2
- 230000037431 insertion Effects 0.000 claims 1
- 238000003780 insertion Methods 0.000 claims 1
- 230000000712 assembly Effects 0.000 description 6
- 238000000429 assembly Methods 0.000 description 6
- 239000000446 fuel Substances 0.000 description 5
- 238000003466 welding Methods 0.000 description 3
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 238000005452 bending Methods 0.000 description 1
- 238000005219 brazing 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】
この発明は原子炉に用いる核燃料集合体に関
し、特に直交格子組みされた複数の帯板とその四
辺の外板とからなる支持格子を備えた核燃料集合
体の支持格子コーナー部の干渉防止のための改良
構造に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear fuel assembly used in a nuclear reactor, and more particularly to a support grid corner of a nuclear fuel assembly equipped with a support grid consisting of a plurality of orthogonal grid plates and outer plates on the four sides thereof. This invention relates to an improved structure for preventing interference between parts.
従来より知られている核燃料集合体において
は、その支持格子が、中板としての複数の薄帯板
を直交格子組みしたものに、その外周四辺を囲む
4枚の帯板外板をとりつける構造となつており、
外板同士は格子組み外周のコーナー部にて端部同
士の重ね合せをスポツト溶接するなどして接続固
定しれている。すなわち第1図はこの従来例のコ
ーナー部を示すもので、1は中板としての格子組
みされた帯板、2,2′は1つのコーナ部にて端
部同士が重ね合せ部3において溶接されて上記格
子組み外周に取付けられた2枚の隣接する外板で
ある。 In conventionally known nuclear fuel assemblies, the support lattice has a structure in which four outer plates of strips surrounding the four sides of the outer periphery are attached to a plurality of thin strip plates as the middle plate arranged in an orthogonal lattice. It's getting old,
The outer panels are connected and fixed to each other by spot welding the overlapped ends at the corners of the outer periphery of the lattice structure. That is, Fig. 1 shows the corner part of this conventional example, where 1 is a strip plate with a lattice structure as the middle plate, and 2 and 2' are welded at the overlapping part 3 at one corner part. These are two adjacent outer panels attached to the outer periphery of the lattice structure.
従来の支持格子は第1図に示すようにコーナー
セル4も内域部のセル5および辺部のセル6と同
様に薄板同士の格子枡目によつて矩形に形成さ
れ、重ね合せ部3における外板同士の接合を抵抗
スポツト溶接およびその後のロー付ないしはTIG
溶接により強固に行ない、さらにコーナー部につ
いては炉内で隣接する他の燃料集合体の支持格子
との引掛りを防止するために重ね合せ部3で面取
り形状にするのが普通である。しかしながら寿命
中期での燃料集合体の交換等の取扱いに際しては
燃料集合体の曲り等の原因で他の燃料集合体の支
持格子との重なり合いが生じ、その状態のままで
燃料集合体を引抜いたり挿入したりして装荷作業
を行なうと支持格子同士の干渉によつて破損が生
じる恐れが多い。すなわち、上記のような支持格
子を備えた核燃料集合体では、第2図に示すよう
に支持格子の外周部のセル、つまり辺部のセル6
とコーナーセル4に挿通されて支持される核燃料
棒などの棒状要素7の外側面に対して帯板外板
2,2′が張り出し、特にコーナーセルの外板角
隅部の重ね合せ部3は辺部での張り出し寸法L1
よりも大きな寸法L2で張り出すことになり、ま
た辺部については第1図に示したように外板上下
縁に内方へ傾斜した案内羽根8が設けられるから
干渉による引掛りが防止されるものの、コーナー
部ではこのような案内羽根を設ける寸法的な余裕
がないので、核燃料集合体が使用中に曲りを生じ
たりすると大きく張り出した角隅部の外板上下縁
が装荷作業時に他の核燃料集合体の支持格子の外
板に引掛り、損傷を起すわけである。 In the conventional support grid, as shown in FIG. Resistance spot welding and subsequent brazing or TIG to join the outer panels
This is done firmly by welding, and the corner portions are usually chamfered at the overlapping portions 3 to prevent them from catching on the support grids of other adjacent fuel assemblies in the furnace. However, when handling fuel assemblies such as replacing them in the middle of their service life, the fuel assemblies may overlap with the support grids of other fuel assemblies due to bending, etc., and the fuel assemblies may be pulled out or inserted in that state. If the loading work is carried out by doing so, there is a high risk that damage will occur due to interference between the support grids. That is, in a nuclear fuel assembly equipped with a support grid as described above, as shown in FIG.
The strip outer plates 2 and 2' protrude from the outer surface of the rod-like element 7, such as a nuclear fuel rod, which is inserted into the corner cell 4 and supported, and in particular, the overlapping portion 3 at the corner corner of the outer plate of the corner cell is Overhang dimension at the side L 1
In addition, as shown in Fig. 1 , guide vanes 8 that are inclined inward are provided on the upper and lower edges of the outer panel to prevent them from getting caught due to interference. However, there is not enough dimensional space to install such guide vanes at the corners, so if the nuclear fuel assembly bends during use, the upper and lower edges of the outer skin at the corners, which protrude greatly, may be exposed to other objects during loading. It gets caught on the outer plate of the support grid of the nuclear fuel assembly, causing damage.
この発明は上述の問題点を解決するためになさ
れたもので、支持格子の角隅部の張り出しを極限
まで小さくし、装荷作業時の引掛りによる損傷を
起さないようにすることを目的としている。 This invention was made in order to solve the above-mentioned problems, and its purpose is to minimize the protrusion of the support grid at the corners, and to prevent damage caused by catching during loading work. There is.
この発明を実施例図面と共に説明すれば、第3
図において支持格子10の内域部および辺部のセ
ルに挿通される核燃料棒等の棒状要素7と同等外
径の別の棒状要素7aをコーナーセルに挿通する
ものであつて、該棒状要素は、支持格子対応部以
外の核燃料要素部71と、支持格子対応部のセグ
メント72との連結構造をもつ核燃料棒であり、
上記セグメント72はそれ自身がジルコニウム合
金等の非核分裂物質の合金で構成されている。 If this invention is explained along with the drawings of the embodiment, the third
In the figure, another rod-shaped element 7a having the same outer diameter as the rod-shaped element 7, such as a nuclear fuel rod, inserted into the inner region and side cells of the support grid 10 is inserted into the corner cell. , a nuclear fuel rod having a connection structure of a nuclear fuel element part 71 other than the support grid corresponding part and a segment 72 of the support grid corresponding part,
The segment 72 itself is composed of an alloy of non-fissile material such as a zirconium alloy.
第4図はこの発明の核燃料集合体に用いられる
支持格子10のコーナー部を示す斜視図で、上記
棒状要素7,7aと組合された場合の横断面が第
5図に示されている。すなわち支持格子10はそ
のコーナーセル4の外板が内部の棒状要素7aの
セグメント71の外面に接するように曲げられて
大きな面取り部11を形成し、辺部のセル6など
の弾性支持部12に代つてこの面取り部11がそ
れ自身の弾性により格子帯板1の剛性支持部9に
対してセグメント72部分を弾圧するコーナーセ
ル弾性支持部として機能するようになされてい
る。 FIG. 4 is a perspective view showing a corner portion of the support grid 10 used in the nuclear fuel assembly of the present invention, and FIG. 5 shows a cross section when combined with the rod-like elements 7, 7a. That is, the support grid 10 is bent so that the outer plate of the corner cell 4 is in contact with the outer surface of the segment 71 of the internal rod-shaped element 7a to form a large chamfered part 11, and the elastic support part 12 such as the cell 6 on the side part is bent. Instead, this chamfered portion 11 functions as a corner cell elastic support portion that presses the segment 72 portion against the rigid support portion 9 of the lattice strip 1 by its own elasticity.
上記面取り部11は図示の例では曲面を形成し
ているが、これは平担な面を形成するものであつ
てもよく、いずれにせよ外板2のコーナー部が支
持格子内方へ大きく逃げて外周隣接辺同士を滑ら
かに連結することになる。またセグメント72と
外板の面取り部とを溶接してもよく、この場合は
コーナーセル内の剛性支持部9は不要である。 Although the chamfered portion 11 forms a curved surface in the illustrated example, it may also form a flat surface, and in any case, the corner portion of the outer panel 2 has a large escape inward from the support grid. This will smoothly connect the adjacent outer edges. Furthermore, the segments 72 and the chamfered portions of the outer panel may be welded together, and in this case, the rigid support portions 9 in the corner cells are not required.
以上に述べたように支持格子のコーナーセル内
において核燃料棒が非核分裂物質製のセグメント
からなつているので、このセグメントは発熱せ
ず、従つて支持格子外板と直接広い面積で接触さ
せることができ、この結果支持格子コーナー部の
外板を大巾に内方へ逃がすことができ、核燃料集
合体の支持格子コーナー部の張り出しが無くな
り、装荷作業時の干渉による引掛りが防止される
ものである。 As mentioned above, since the nuclear fuel rods in the corner cells of the support grid are made of segments made of non-fissile material, these segments do not generate heat and therefore can be brought into direct contact over a large area with the support grid outer plate. As a result, the outer plate of the corner of the support grid can be moved inward by a large width, eliminating the overhang of the corner of the support grid of the nuclear fuel assembly, and preventing it from getting caught due to interference during loading work. be.
第1図は従来の核燃料集合体の支持格子のコー
ナー部を示す斜視図、第2図はそのコーナー部の
棒状要素の配列を示す横断面図、第3図はこの発
明の一実施例に係る核燃料集合体のコーナー部の
棒状要素を示す部分正面図、第4図はこの発明の
核燃料集合体に用いる支持格子の一実施例を示す
コーナー部の斜視図、第5図は第3図の棒状要素
を第4図の支持格子と組合せた場合のコーナー部
の配列を示す横断面図である。
1:帯板、2,2′:帯板外板、4:コーナー
セル、5:内域部のセル、6:辺部のセル、7,
7a:棒状要素、71:核燃料要素部、72:セ
グメント、8:案内羽根、10:支持格子、1
1:面取り部。
FIG. 1 is a perspective view showing a corner portion of a support grid of a conventional nuclear fuel assembly, FIG. 2 is a cross-sectional view showing an arrangement of rod-like elements at the corner portion, and FIG. 3 is a perspective view showing an arrangement of rod-like elements at the corner portion. FIG. 4 is a partial front view showing a rod-like element at a corner of a nuclear fuel assembly; FIG. 4 is a perspective view of a corner portion showing an embodiment of a support grid used in the nuclear fuel assembly of the present invention; FIG. 5 is a cross-sectional view showing the corner arrangement when the element is combined with the support grid of FIG. 4; 1: Strip plate, 2, 2': Strip plate outer plate, 4: Corner cell, 5: Inner region cell, 6: Side cell, 7,
7a: Rod-shaped element, 71: Nuclear fuel element portion, 72: Segment, 8: Guide vane, 10: Support grid, 1
1: Chamfered part.
Claims (1)
板外板で囲周し格子枡目を核燃料棒等の棒状要素
の挿通支持用のセルとした支持格子を有する核燃
料集合体において、上記支持格子の角隅部のコー
ナーセルに挿通される棒状要素が、支持格子対応
部以外の核燃料要素部と、支持格子対応部の非核
分裂物質合金製セグメント部とを軸方向につない
だ連結構造をもつ核燃料棒からなり、支持格子の
コーナーセルの帯板外板が上記セグメント部外面
に接するように滑らかに曲げられて支持格子外周
の隣接外辺間を連結してなることを特徴とする核
燃料集合体。1. In a nuclear fuel assembly having a support lattice in which a plurality of strips are arranged in a lattice, the four sides of the outer periphery of the lattice are surrounded by strip outer plates, and the lattice cells are cells for insertion and support of rod-shaped elements such as nuclear fuel rods, the above-mentioned A connecting structure in which a rod-like element inserted into a corner cell of a support grid axially connects the nuclear fuel element part other than the support grid corresponding part and the non-fissile material alloy segment part of the support grid corresponding part is formed. 1. A nuclear fuel assembly comprising nuclear fuel rods having a support lattice, wherein the strip outer plates of the corner cells of the support lattice are smoothly bent so as to be in contact with the outer surface of the segment portion, and adjacent outer edges of the outer periphery of the support lattice are connected. body.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP56005989A JPS57120890A (en) | 1981-01-20 | 1981-01-20 | Nuclear fuel assembly |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP56005989A JPS57120890A (en) | 1981-01-20 | 1981-01-20 | Nuclear fuel assembly |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS57120890A JPS57120890A (en) | 1982-07-28 |
JPS6312549B2 true JPS6312549B2 (en) | 1988-03-19 |
Family
ID=11626197
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP56005989A Granted JPS57120890A (en) | 1981-01-20 | 1981-01-20 | Nuclear fuel assembly |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS57120890A (en) |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5666795A (en) * | 1979-11-02 | 1981-06-05 | Mitsubishi Atomic Power Ind | Fuel assembly |
-
1981
- 1981-01-20 JP JP56005989A patent/JPS57120890A/en active Granted
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5666795A (en) * | 1979-11-02 | 1981-06-05 | Mitsubishi Atomic Power Ind | Fuel assembly |
Also Published As
Publication number | Publication date |
---|---|
JPS57120890A (en) | 1982-07-28 |
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