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JPS61219893A - Support lattice for reactor fuel aggregate - Google Patents

Support lattice for reactor fuel aggregate

Info

Publication number
JPS61219893A
JPS61219893A JP60063104A JP6310485A JPS61219893A JP S61219893 A JPS61219893 A JP S61219893A JP 60063104 A JP60063104 A JP 60063104A JP 6310485 A JP6310485 A JP 6310485A JP S61219893 A JPS61219893 A JP S61219893A
Authority
JP
Japan
Prior art keywords
support grid
welding
fuel assembly
outer edge
reactor fuel
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.)
Granted
Application number
JP60063104A
Other languages
Japanese (ja)
Other versions
JPH0375078B2 (en
Inventor
信行 上野
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.)
Nuclear Fuel Industries Ltd
Original Assignee
Nuclear Fuel Industries Ltd
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 Nuclear Fuel Industries Ltd filed Critical Nuclear Fuel Industries Ltd
Priority to JP60063104A priority Critical patent/JPS61219893A/en
Publication of JPS61219893A publication Critical patent/JPS61219893A/en
Publication of JPH0375078B2 publication Critical patent/JPH0375078B2/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

  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 (産業上の利用分野) 本発明は原子炉燃料集合体用の支持格子の改良に関する
ものである。
DETAILED DESCRIPTION OF THE INVENTION Field of the Invention The present invention relates to improvements in support grids for nuclear reactor fuel assemblies.

(従来の技術) 原子炉燃料集合体には第9図に示す如く燃料棒(1)同
志を所定の間隔を隔てて上下ノズル(3) (41間で
確実に保持し、原子炉運転中、同等支障なく十分に性能
を発揮できるように支持格子(2)が燃料棒長手方向に
複数個設けられている。
(Prior art) As shown in Fig. 9, in a nuclear reactor fuel assembly, fuel rods (1) are securely held between upper and lower nozzles (3) (41) at a predetermined interval, and during reactor operation, A plurality of support grids (2) are provided in the longitudinal direction of the fuel rods so that the fuel rods can exhibit sufficient performance without any problems.

この支持格子は通常、多数の燃料棒を軸方向平行に整列
させ、発熱する燃料棒表面から除熱するために燃料棒間
に必要なギャップを保持して冷却材の流れを保証する働
きをするものであり、従来一般に鉄−クロム−ニッケル
系超合金(商品名インコネル)やジルコニウム系合金(
ジルカロイ−2またはジルカロイ−4など)の通常、0
.25璽鳳〜0.6n程度の薄板をプレス加工で所定形
状に成型し、第10図に示すように弾性突起(7)や固
定突起(7)を備え、スリン) (6) (6′)を付
した2群の帯板を中板(51(51として、これをその
組立用スリット(6)(6′)同志を嵌合させて格子状
に組立てた後、中板の交わる部分上下をTIG溶接、レ
ーザー溶接、電子ビーム溶接など、溶接やロー付などの
冶金的接合法で結着一体化することによって製作されて
いる。
This support grid typically serves to align a large number of fuel rods axially in parallel, maintaining the necessary gaps between the fuel rods to remove heat from the heat-generating surfaces of the fuel rods, and to ensure coolant flow. Conventionally, iron-chromium-nickel superalloys (trade name Inconel) and zirconium alloys (
Zircaloy-2 or Zircaloy-4), usually 0
.. A thin plate of approximately 0.25 mm to 0.6 mm is formed into a predetermined shape by press processing, and as shown in Fig. 10, it is equipped with elastic protrusions (7) and fixed protrusions (7). After assembling the two groups of strip plates marked with the middle plate (51) into a lattice shape by fitting the assembly slits (6) and (6') together, the upper and lower parts where the middle plates intersect are They are manufactured by bonding and integrating them using metallurgical joining methods such as TIG welding, laser welding, and electron beam welding, as well as welding and brazing.

ところで、かかる支持格子には前述の働きからその性能
として必要な強度を有し、しかも冷却材の流動に対して
は出来るだけ抵抗が少ないことが求められるが、この両
特性は通常、相反する特性となる。
By the way, such support grids are required to have the strength necessary for their performance due to the above-mentioned function, and also to have as little resistance as possible to the flow of coolant, but these two characteristics are usually contradictory. becomes.

即ち、強度を増すために材料の板厚を増加すれば冷却材
の流路断面積が減少し、流水抵抗、即ち冷却材圧力損失
の値が大きくなる。
That is, if the thickness of the material is increased in order to increase the strength, the cross-sectional area of the coolant flow path decreases, and the flow resistance, that is, the value of the coolant pressure loss increases.

そこで、支持格子には通常、この両者のバランスを考え
た設計が考えられなければならないが、相反する2つの
特性の最適な組合わせは板厚あるいは燃料棒を支承する
突起物等の形状を考慮して極めて狭い範囲の設計条件の
中で模索せざるを得ない状況であった。
Therefore, support grids usually have to be designed with a balance between the two, but the optimal combination of these two contradictory characteristics requires consideration of the plate thickness and the shape of the protrusions that support the fuel rods. Therefore, we were forced to search within an extremely narrow range of design conditions.

そして、この場合、中板については、金属薄板を組合わ
せた状態で板の交わる部分を溶融し、第3図に示すよう
な溶接ナゲツト(9)を形成して直交する仮同志を接合
固着するが、この溶接ナゲツトの寸法については従来よ
り支持格子特性に影響を与える要因と推定されてはいた
が、単に欠陥のない良好な溶接を得るということはあっ
ても積極的にこれをコントロールしようとする考えは示
されたことはなかった。
In this case, for the middle plate, the intersecting parts of the metal thin plates are melted to form a welding nugget (9) as shown in Fig. 3, and the orthogonal temporary members are joined and fixed. However, although the dimensions of this weld nugget have traditionally been assumed to be a factor that affects the support grid properties, efforts have been made to actively control this, even if it is simply to obtain a good weld without defects. The idea of doing so was never expressed.

(発明が解決しようとする問題点) 本発明は上述の如き現状に対処し、従来考慮されること
のなかった前記溶接ナゲツトの寸法関係に着目し、該寸
法をコントロールすることによって支持格子の前記相反
する2つの特性のバランスをはかり冷却材の流動抵抗が
小さく、かつ強度の大きな支持格子を得ることを目的と
するものである。
(Problems to be Solved by the Invention) The present invention addresses the above-mentioned current situation, focuses on the dimensional relationship of the weld nugget, which has not been considered in the past, and controls the dimensions of the weld nugget. The purpose of this invention is to obtain a support grid with low coolant flow resistance and high strength by balancing two contradictory characteristics.

(問題点を解決するための手段) 即ち、上記目的に適合する本発明の特徴とするところは
、第10図に示された金属薄板よりなる互いに直交する
2群の帯板を中板(51<6として各々の組立用スリッ
ト(6)(6′)を介して格子状に組合わせることによ
って形成され、各正方形状格子セル内には挿通される燃
料棒等を横方向に保持する突起(7)(71を備えた原
子炉燃料集合体用支持格子において、第1〜第3図に示
す前記組立用スリッ) (6) (6’)が互いに嵌合
された中板の交点部分(8)を溶接によって固定し、該
溶接部の溶接ナゲツト(9)寸法を支持格子の外縁部の
溶接個所と、中央部の溶接個所とで前者の寸法を後者の
それに比し大ならしめたことにある。
(Means for Solving the Problems) That is, the feature of the present invention that satisfies the above-mentioned object is that two groups of mutually orthogonal strips made of thin metal plates shown in FIG. <6, which are formed by combining them in a lattice shape through the respective assembly slits (6) and (6'), and each square lattice cell has a projection ( 7) (In the support grid for a reactor fuel assembly equipped with 71, the assembly slits shown in FIGS. 1 to 3) (6) (6') are fitted together at the intersection portions (8) of the middle plates. ) is fixed by welding, and the dimensions of the weld nugget (9) of the welded part are made larger at the welded part at the outer edge of the support grid and at the welded part at the center part. be.

ここで、支持格子の外縁部の溶接個所とは、嵌合される
中板交点部分のうち外周の1列分または2列分を通常と
するが、別設、これに制約されるものではない。そして
、これら外縁部の溶接個所の溶接ナゲツト寸法としては
、中央部の溶接個所の溶接ナゲツト寸法が中板板厚の3
〜5倍程度を好適範囲とするのに対し6〜8倍程度が好
適である。
Here, the welding location on the outer edge of the support grid is usually one or two rows on the outer periphery of the intersection of the middle plates to be fitted, but the welding location is not limited to this. . As for the weld nugget dimensions of these welding points at the outer edges, the weld nugget dimensions of the welding points at the center are 3 times the thickness of the middle plate.
The preferable range is approximately 5 to 5 times, while 6 to 8 times is preferred.

なお、外縁部と中央部は厳密な意味の2段階に限らず、
強度を考慮し、設計が許容されれば3段階以上に分け、
段階的に異ならしめることも可能であり、本発明の含む
ところである。
Note that the outer edge and the center are not limited to two stages in a strict sense;
Considering the strength, if the design allows, divide it into three or more stages,
It is also possible to make the difference stepwise, which is included in the present invention.

前記本発明支持格子を構成する金属薄板材料としては、
例えば、鉄−クロム−ニッケル系超合金あるいはジルコ
ニウム基合金などが挙げられ、適宜選択して用いられる
The thin metal plate material constituting the support grid of the present invention includes:
Examples include iron-chromium-nickel superalloys and zirconium-based alloys, which are appropriately selected and used.

(作 用) 次に上記の如き構成による作用であるが、上記支持格子
は従来の支持格子と同じく燃料集合体においてその長手
方向にわたり複数個が使用される。
(Function) Next, as for the effect of the above-mentioned configuration, a plurality of the support grids are used in the fuel assembly in the longitudinal direction, like conventional support grids.

このとき、前述のように支持格子の特性を考えると、冷
却材圧力損失に関しては流路断面積が大きい方が好まし
い。
At this time, considering the characteristics of the support grid as described above, it is preferable that the flow passage cross-sectional area be large in terms of coolant pressure loss.

ところが、中板交点溶接個所の溶接ナゲツトは第3図か
ら明らかなように冷却材の流路を狭める結果を生ずるの
で小さい方が良いことになる。
However, as is clear from FIG. 3, the weld nuggets at the intermediate plate intersection welds narrow the coolant flow path, so the smaller the weld nuggets, the better.

一方、逆に支持格子強度面からは溶接ナゲツトが大きい
方が接合部強度が強くなり、ひいては支持格子全体の強
度を増大する。
On the other hand, from the viewpoint of support grid strength, the larger the weld nugget, the stronger the joint strength, which in turn increases the strength of the support grid as a whole.

そこで、支持格子の強度について先ず考察したところ、
静的荷重に対する強度についても云えることであるが、
特に地震が発生した場合等に支持格子に作用する衝撃荷
重に対する強度は支持格子外周部分の接合部の強度に大
きく依存することが判明した。
Therefore, we first considered the strength of the support grid, and found that
The same can be said about the strength against static loads,
It has been found that the strength against shock loads that act on the support grid, especially in the event of an earthquake, is largely dependent on the strength of the joints on the outer periphery of the support grid.

第11図はかかる衝撃試験の結果、支持格子が破損し、
変形している状態を示し、このことから外周部分の強度
がとりわけ重要であることが理解される。
Figure 11 shows that as a result of such an impact test, the support grid was damaged;
It shows a deformed state, and from this it can be understood that the strength of the outer peripheral portion is particularly important.

又、更に加圧水型原子炉燃料集合体の場合には第1図に
示されるように通常、第3列目より内側に一重丸で示し
た制御棒案内管挿通セルを設けるのが普通であるが、制
御棒案内管は冷却材喪失事故などによって原子炉を緊急
停止しなければならないような場合、自由に制御棒が挿
入されるべく通路を確保する必要があり、制御棒案内管
挿通セルより外側を強固な構造となして、これを保護す
るのは重要なことであ。
Furthermore, in the case of a pressurized water reactor fuel assembly, as shown in Figure 1, it is normal to provide a control rod guide tube insertion cell, indicated by a single circle, inside the third row. It is necessary to secure a passage for the control rod guide tube so that the control rods can be freely inserted in the event that the reactor has to be stopped urgently due to a loss of coolant accident, etc. It is important to have a strong structure and protect it.

一方、冷却材圧力損失について考えれば冷却材圧力損失
は全体の流路断面積によって略決まってしまうので流路
断面積が大きいこと、即ち、溶接ナゲツト寸法が小さい
方が好ましいことは勿論で、これはその配置によって影
響されるところは極めて少ない。
On the other hand, considering the coolant pressure loss, the coolant pressure loss is approximately determined by the overall cross-sectional area of the flow path, so it goes without saying that it is preferable that the cross-sectional area of the flow path is large, that is, the weld nugget size is small. is very little affected by its placement.

かくして、前記本発明の支持格子の構成、即ち外周部の
1列、好ましくは2列分の中板交点溶接個所の溶接ナゲ
ツト寸法を設計の許す範囲で大きくし、一方、その内側
の中央部の溶接個所では、溶接ナゲツト寸法をなるべく
小さくすることによって全体で溶接ナゲツト寸法が一様
な大きさに形成された支持格子よりも機械的強度が大き
く、かつ冷却材圧力損失の小さな作用を奏する。
Thus, the configuration of the support grid of the present invention is such that the weld nugget size of one row, preferably two rows of intermediate plate intersection welding points on the outer periphery is increased to the extent permitted by the design, while At the welding location, by making the weld nugget size as small as possible, the mechanical strength is greater than that of a support grid in which the weld nugget size is uniform throughout, and the coolant pressure loss is reduced.

(実施例) 以下、更に本発明支持格子の具体的実施例を添付図面に
従って説明する。
(Example) Hereinafter, specific examples of the support grid of the present invention will be further described with reference to the accompanying drawings.

第1図は本発明支持格子における溶接個所の位置を示し
ており、(2)は支持格子で金属薄板よりなる互いに直
交する2群の帯板を中板(5) (5)として第10図
の如く各々の組立用スリット61 <6)を介して格子
状に組合わせることによって形成され、各正方形状格子
セル内には、制御棒案内管挿通セル(11)には−電光
で示す制御棒案内管が、又、計装用案内管挿通セル(1
2)には二重光で示す計装用案内管が夫々挿入される。
Figure 1 shows the positions of welding points in the support grid of the present invention, and (2) shows the support grid with two groups of mutually orthogonal strips made of thin metal plates as the middle plate (5) (5). The control rods are assembled in a grid pattern through the respective assembly slits 61 (<6) as shown in FIG. The guide tube also has an instrumentation guide tube insertion cell (1
2) are each inserted with an instrumentation guide tube shown in double light.

そして、上記2群の中板(5)晶からその組立用スリッ
トによって互いに嵌合される中板交点部分(8)はTI
G溶接、レーザー溶接、電子ビーム溶接など公知の溶接
手段によって溶接固定され、該溶接個所には第3図に示
す如き溶接ナゲツト(9)が形成される。
The intersecting points (8) of the intermediate plates (8) that are fitted to each other through the assembly slits from the intermediate plates (5) of the two groups are TI.
It is welded and fixed by known welding means such as G welding, laser welding, and electron beam welding, and a weld nugget (9) as shown in FIG. 3 is formed at the welding location.

本発明は、この溶接ナゲツトに重要な特徴をもっており
、第1図において小さな丸印で示される支持格子外縁部
、図では外周2列分の溶接ナゲツト寸法が内部の中央部
溶接個所の溶接ナゲツト寸法より大きく作られる。例え
ば、外縁部の溶接個所の溶接ナゲツト寸法、即ち、第3
図における(a)は中板板厚(1)の6倍〜8倍であり
、一方、中央部における溶接個所の上記溶接ナゲツト寸
法は中板板厚(1)の3倍〜5倍である。
The present invention has an important feature in this welding nugget, in which the dimensions of the welding nugget at the outer edge of the support grid indicated by small circles in FIG. made larger. For example, the weld nugget size of the welding location on the outer edge, that is, the third
(a) in the figure is 6 to 8 times the thickness of the middle plate (1), and on the other hand, the weld nugget size at the welding point in the center is 3 to 5 times the thickness of the middle plate (1). .

なお、この溶接ナゲツト寸法は固定的ではなく適宜制御
可能であり、通常の溶接条件、即ち、溶接電流や溶接時
間をパラメータとして溶接入熱の大きさを適当に選ぶこ
とによって達成される。
Note that this weld nugget size is not fixed but can be controlled as appropriate, and is achieved by appropriately selecting the magnitude of welding heat input using normal welding conditions, that is, welding current and welding time as parameters.

また、第4図、第5図に示すように溶接ナゲフトを形成
するための溶融金属材料を供給する溶接タブaωQOI
を予め、中板(5) tgtのプレス加工で設けておく
場合には、該溶接タブαω06の寸法、形状を、得るべ
き溶接ナゲツトの大きさに合わせて調整しておけば一層
容易にコントロールすることができる。
In addition, as shown in FIGS. 4 and 5, a welding tab aωQOI for supplying molten metal material for forming a welding nageft is provided.
If the intermediate plate (5) is prepared in advance by TGT press working, it will be easier to control the welding tab αω06 by adjusting its dimensions and shape according to the size of the welding nugget to be obtained. be able to.

次に0.4 tm板厚のインコネル−718を使用して
加圧水型原子炉燃料集合体用の支持格子を作り、その強
度、冷却材圧力損失値を試験した結果を第6図、第7図
に示す。
Next, a support grid for a pressurized water reactor fuel assembly was made using Inconel-718 with a thickness of 0.4 tm, and its strength and coolant pressure loss values were tested. Figures 6 and 7 show the results. Shown below.

なお、溶接法はTIG溶接を用いた。又、図において破
線、2点鎖線は夫々本発明に係る外縁部中板交点部分の
うち、1列分、2列分の溶接個所。
Note that TIG welding was used as the welding method. Further, in the figure, the broken line and the two-dot chain line represent welding points for one row and two rows, respectively, of the intersection of the outer edge middle plate according to the present invention.

溶接ナゲツト寸法を8t(tは中板板厚)に固定し、そ
れよりも内側の中央部溶接個所の溶接ナゲツトを横軸に
示される寸法に変化させた場合の挙動を示し、一方、実
線は溶接ナゲツト寸法が内外均一なまま、その寸法が変
化した比較例の場合を示す。
The behavior is shown when the weld nugget size is fixed at 8t (t is the thickness of the middle plate) and the weld nugget at the central welding point on the inside is changed to the size shown on the horizontal axis.On the other hand, the solid line is A comparative example is shown in which the dimensions of the weld nugget remain uniform inside and outside, but the dimensions change.

先ず、支持格子強度の挙動を示す第6図から比較例では
中板板厚をtとしたとき、ナゲツト寸法が3tあたりに
達するまでは急激に強度が上昇し、3t〜8tの間では
比較的緩やかに増加し、10tあたりから又、強度増加
の程度が大きくなるが、本発明によるものでは外縁部2
列分の溶接ナゲツトを8tにした場合、中央部分では2
tになるまでは殆ど強度の低下は見られないし、1列分
の場合でも3を以上では実質的に強度の低下がないこと
が理解される。
First, from Figure 6, which shows the behavior of the support grid strength, in the comparative example, when the thickness of the middle plate is t, the strength increases rapidly until the nugget size reaches around 3t, and is relatively low between 3t and 8t. The strength increases gradually, and the degree of strength increase increases from around 10t, but in the case of the present invention, the strength increases at the outer edge 2.
If the welding nugget for the row is 8t, the center part will be 2t.
It is understood that almost no decrease in strength is observed up to t, and that there is virtually no decrease in strength beyond 3 even in the case of one row.

一方、冷却材圧力損失値に関しては第7図より比較例の
場合にはほぼ放物線に近い曲線形状でナゲツト寸法8t
あたりから急激な上昇が見られるが本発明の場合には内
外周とも前記溶接ナゲツト寸法が均一で小さい場合に比
べて外縁部の外周1列。
On the other hand, regarding the coolant pressure loss value, as shown in Fig. 7, in the case of the comparative example, the curve shape is almost parabolic, and the nugget size is 8t.
However, in the case of the present invention, compared to the case where the dimensions of the weld nuggets are uniform and small on both the inner and outer circumferences, there is a sharp rise from around the outer circumference of the outer edge.

2列共にナゲツト寸法が8tとなったときにもそれ程大
きく増加しないことが分かる。
It can be seen that even when the nugget size in both rows is 8t, it does not increase so much.

従って、本発明による支持格子は従来のナゲツト寸法が
均一な場合にして支持格子の特性のバランスにおいて優
れていることが分かる。
Therefore, it can be seen that the support grid according to the present invention is superior in the balance of properties of the support grid when the conventional nugget size is uniform.

又、第8図は外周部2列分を外縁部としそれより内側を
中央部として外縁部と中央部とで溶接ナゲツト寸法を変
えたときの強度及び圧力損失値のマツプである。
FIG. 8 is a map of the strength and pressure loss values when the weld nugget dimensions are changed between the outer edge and the center, with two rows of the outer periphery as the outer edge and the inner side as the center.

この図より最適な組合わせとしては外縁部の溶接ナゲツ
ト寸法が6t〜8t、中央部溶接ナゲツト寸法が3t〜
5tであると言うことができる。この好適条件範囲を第
8図交叉斜線で示す。
From this figure, the optimal combination is that the outer edge weld nugget size is 6t~8t, and the center weld nugget size is 3t~
It can be said that it is 5t. This range of preferable conditions is shown by crossed diagonal lines in FIG.

ここで、中央部溶接ナゲツト寸法の下限を3tとしたの
は支持格子用中板のように金属薄板の帯板溶接において
は余り小さな溶接はバラツキが太き(なる傾向にあり、
製品の生産用に品質の揃った溶接を多量に実施すること
が困難であるという理由による。
Here, the lower limit of the center weld nugget size was set at 3t because when welding strips of thin metal plates, such as middle plates for support grids, welds that are too small tend to have wide variations.
This is because it is difficult to carry out large quantities of welding of uniform quality for product production.

なお、上記説明はインコネル−718を使用した場合で
あるが、別途、実施した0、45m板厚のジル lカロ
イ−4中板をレーザー溶接法で接合した支持格子におけ
る試験でも全く同様の結果を得た。
The above explanation is for the case where Inconel-718 is used, but a separate test using a support grid made by joining Zirl Caloy-4 medium plates with a thickness of 0 and 45 m using a laser welding method yielded exactly the same results. Obtained.

かくして、以上より本発明による支持格子が優れた特性
をもつことが理解される。
Thus, it can be seen from the above that the support grid according to the present invention has excellent properties.

(発明の効果) 本発明は以上のように燃料集合体用支持格子において、
溶接部の溶接ナゲツト寸法に着目し、支持格子の外縁部
と中央部の溶接ナゲツト寸法を異ならしめ、前者を後者
より大ならしめたものであり、支持格子中板交点部分溶
接部の溶接ナゲツト寸法をコントロールし、外縁部で大
きく、中央部で小さくしたことにより、支持格子に要求
される特性で相反する2つの特性、即ち、機械的強度が
太き(、冷却材圧力損失の小さいという相反する特性を
強度は外縁部で、一方、圧力損失は中央部で夫々保証し
て2つながら良好に満足する顕著な効果を奏し、燃料集
合体用支持格子の安全性並びに機能の面で今後にお、け
る実効が大いに期待される。
(Effects of the Invention) As described above, the present invention provides a support grid for a fuel assembly.
Focusing on the weld nugget size of the welded part, the weld nugget size at the outer edge and center of the support grid is made different, and the former is made larger than the latter. By controlling and making it larger at the outer edge and smaller at the center, we are able to meet the two contradictory properties required for support grids: high mechanical strength (high mechanical strength, low coolant pressure drop). As for the characteristics, the strength is guaranteed at the outer edge and the pressure loss is guaranteed at the center, respectively.Although the two characteristics are both guaranteed, the result is a remarkable effect that satisfies both the safety and function of support grids for fuel assemblies. It is highly anticipated that this will be effective.

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

第1図は本発明が適用される支持格子の概要平面図、第
2図は支持格子中板組立用スリット嵌合状態部分平面図
、第3図は同支持格子中板交点部分溶接後の部分平面図
、第4図及び第5図は支持格子中板を形成する各帯板の
溶接タブ形状を示す部分図、第6図は溶接ナゲツト寸法
と支持格子強度との関係を示す図表、第7図は溶接ナゲ
ツト寸法と支持格子による冷却材圧力損失値との関係を
示す図表、第8図は外縁部、中央部溶接ナゲツト寸法の
支持格子強度及び冷却材圧力損失値への影響を示す図表
、第9図は燃料集合体の全体概要図、第10図は支持格
子中板組立用スリット嵌合状態説明図、第11図は支持
格子強度試験後変形状況説明図である。 (1)・・・燃料棒。 (2)・・・支持格子。 (3)・・・上部ノズル。 (4)・・・下部ルズル、 (51(5’l・・中板(帯板)。 (61tj+・・組立用スリット。 (7)・・・弾性突起。 (7)・・・固定突起。 (8)・・・交点部分。 (9)・・・溶接ナゲツト、   ・ α0)06・・溶接タブ。 ゝζ−L7 第1図 第6図 篤7I21 第8図 草II図
Fig. 1 is a schematic plan view of a support grid to which the present invention is applied, Fig. 2 is a partial plan view of a state in which slits for assembling the support grid middle plate are fitted, and Fig. 3 is a section after welding the intersection points of the support grid middle plate. A plan view, FIGS. 4 and 5 are partial views showing the welding tab shape of each strip forming the support grid intermediate plate, FIG. 6 is a chart showing the relationship between weld nugget dimensions and support grid strength, and FIG. Figure 8 is a chart showing the relationship between weld nugget dimensions and coolant pressure loss values due to support grids; Figure 8 is a chart showing the influence of outer edge and center weld nugget dimensions on support grid strength and coolant pressure loss values; FIG. 9 is an overall schematic diagram of the fuel assembly, FIG. 10 is an explanatory diagram of a state in which slits for assembling the support grid intermediate plate are fitted, and FIG. 11 is an explanatory diagram of the state of deformation after the support grid strength test. (1)...Fuel rod. (2)...Support grid. (3)...Top nozzle. (4)...Lower part, (51(5'l...Middle plate (band plate). (61tj+...Slit for assembly. (7)...Elastic protrusion. (7)...Fixing protrusion. (8)...Intersection part. (9)...Weld nugget, ・α0)06...Weld tab. ゝζ-L7 Figure 1 Figure 6 Atsushi 7I21 Figure 8 Grass II Figure

Claims (1)

【特許請求の範囲】 1、金属薄板からなる直交する2群の帯板を中板として
各々の組立用スリットを介して格子状に組合わせること
によって形成され、各正方形状格子セル内には燃料棒等
を横方向に保持する突起を備えた原子炉燃料集合体用支
持格子において、前記の組立用スリットが互いに嵌合さ
れた中板の交点部分を溶接によって固定し、該溶接部の
溶接ナゲット寸法を支持格子の外縁部の溶接個所と、中
央部の溶接個所とで、前者寸法を後者のそれに比し大な
らしめたことを特徴とする原子炉燃料集合体用支持格子
。 2、支持格子外縁部の溶接個所が中板交点部分のうち、
外周の1〜2列分である特許請求の範囲第1項記載の原
子炉燃料集合体用支持格子。 3、外縁部の溶接個所の溶接ナゲット寸法が中板板厚の
6〜8倍であり、中央部の溶接個所の溶接ナゲット寸法
が中板板厚の3〜5倍である特許請求の範囲第1項又は
第2項記載の原子炉燃料集合体用支持格子。 4、金属薄板が鉄−クロム−ニッケル系超合金薄板であ
る特許請求の範囲第1項、第2項又は第3項記載の原子
炉燃料集合体用支持格子。 5、金属薄板がジルコニウム基合金薄板である特許請求
の範囲第1項、第2項、又は第3項記載の原子炉燃料集
合体用支持格子。
[Scope of Claims] 1. It is formed by combining two orthogonal groups of strips made of metal thin plates into a lattice shape through assembly slits as middle plates, and each square lattice cell has a fuel cell. In a support grid for a nuclear reactor fuel assembly that is equipped with projections that laterally hold rods, etc., the intersecting points of the middle plates where the assembly slits are fitted together are fixed by welding, and a weld nugget is formed at the welded portion. 1. A support grid for a nuclear reactor fuel assembly, characterized in that the dimensions of a welded location on the outer edge of the support grid and a welded location in the center of the support grid are larger than those of the latter. 2. The welding point of the outer edge of the support grid is at the intersection of the middle plate,
The support grid for a nuclear reactor fuel assembly according to claim 1, which is one to two rows on the outer periphery. 3. The size of the weld nugget at the welded location on the outer edge is 6 to 8 times the thickness of the middle plate, and the size of the welded nugget at the welded location in the center is 3 to 5 times the thickness of the middle plate. A support grid for a nuclear reactor fuel assembly according to item 1 or 2. 4. A support grid for a nuclear fuel assembly according to claim 1, 2 or 3, wherein the metal thin plate is an iron-chromium-nickel superalloy thin plate. 5. The support grid for a nuclear fuel assembly according to claim 1, 2, or 3, wherein the thin metal plate is a zirconium-based alloy thin plate.
JP60063104A 1985-03-26 1985-03-26 Support lattice for reactor fuel aggregate Granted JPS61219893A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60063104A JPS61219893A (en) 1985-03-26 1985-03-26 Support lattice for reactor fuel aggregate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60063104A JPS61219893A (en) 1985-03-26 1985-03-26 Support lattice for reactor fuel aggregate

Publications (2)

Publication Number Publication Date
JPS61219893A true JPS61219893A (en) 1986-09-30
JPH0375078B2 JPH0375078B2 (en) 1991-11-28

Family

ID=13219647

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60063104A Granted JPS61219893A (en) 1985-03-26 1985-03-26 Support lattice for reactor fuel aggregate

Country Status (1)

Country Link
JP (1) JPS61219893A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009526977A (en) * 2006-02-18 2009-07-23 アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング Fuel assemblies for pressurized water reactors

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009526977A (en) * 2006-02-18 2009-07-23 アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング Fuel assemblies for pressurized water reactors

Also Published As

Publication number Publication date
JPH0375078B2 (en) 1991-11-28

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