JPH0511873B2 - - Google Patents

Info

Publication number
JPH0511873B2
JPH0511873B2 JP61196778A JP19677886A JPH0511873B2 JP H0511873 B2 JPH0511873 B2 JP H0511873B2 JP 61196778 A JP61196778 A JP 61196778A JP 19677886 A JP19677886 A JP 19677886A JP H0511873 B2 JPH0511873 B2 JP H0511873B2
Authority
JP
Japan
Prior art keywords
support grid
strap
straps
sleeve
fuel assembly
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
Application number
JP61196778A
Other languages
Japanese (ja)
Other versions
JPS6352093A (en
Inventor
Shinobu Okuyama
Fumio Kashimura
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.)
Mitsubishi Nuclear Fuel Co Ltd
Original Assignee
Mitsubishi Nuclear Fuel Co 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 Mitsubishi Nuclear Fuel Co Ltd filed Critical Mitsubishi Nuclear Fuel Co Ltd
Priority to JP61196778A priority Critical patent/JPS6352093A/en
Publication of JPS6352093A publication Critical patent/JPS6352093A/en
Publication of JPH0511873B2 publication Critical patent/JPH0511873B2/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)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)

Description

【発明の詳細な説明】 「産業上の利用分野」 この発明は、複数の燃料棒を支持する原子炉燃
料集合体の支持格子に関する。
DETAILED DESCRIPTION OF THE INVENTION "Field of Industrial Application" This invention relates to a support grid for a nuclear reactor fuel assembly that supports a plurality of fuel rods.

「従来の技術」 従来、この種の原子炉集合体の支持格子として
第6図ないし第8図に示すものが知られている。
``Prior Art'' Hitherto, the support grids shown in FIGS. 6 to 8 have been known as support grids for this type of nuclear reactor assembly.

第6図において、符号1は燃料集合体である。
燃料集合体1は、上下に水平に隔てられた上部ノ
ズル2と、下部ノズル3と、これらの間に配置さ
れた支持格子4と、支持格子4の後述するスリー
ブを通して上部ノズル2及び下部ノズル3を連結
する制御棒案内管5と、支持格子4の後述する格
子空間を通つて配設された燃料棒6とを具備して
なるものである。
In FIG. 6, reference numeral 1 indicates a fuel assembly.
The fuel assembly 1 includes an upper nozzle 2 and a lower nozzle 3 that are horizontally separated from each other, a support grid 4 disposed between these, and a sleeve (to be described later) of the support grid 4 to connect the upper nozzle 2 and the lower nozzle 3. The control rod guide tube 5 connects the fuel rods 6 to the support lattice 4, and the fuel rods 6 are disposed through the lattice spaces of the support lattice 4, which will be described later.

支持格子4は、第7図に示すような長方形状の
薄板にその長手方向と直角な方向に一定間隔ごと
にスリツト7が形成されたストラツプ8を用い
て、スリツト7を互に嵌め合わせて縦横に組ん
で、第8図のように多数の格子空間9が形成され
たものである。格子空間9には、ある間隔をおい
て格子空間9と軸線を一致させて円筒形のスリー
ブ10が装着されている。
The support grid 4 is constructed by using a strap 8 in which slits 7 are formed at regular intervals in a direction perpendicular to the longitudinal direction of a rectangular thin plate as shown in FIG. As shown in FIG. 8, a large number of lattice spaces 9 are formed. A cylindrical sleeve 10 is installed in the grid space 9 with a certain interval and its axis coincides with the grid space 9.

上記構成からなる支持格子4は、スリーブ10
に制御棒案内管5を挿通し、この制御棒案内管5
をスリーブ10に固定して燃料集合体1の骨組を
構成するものである。また、格子空間9に燃料棒
6を挿通してこの燃料棒6を一定間隔おいて互に
平行になるよう支持するものである。
The support grid 4 having the above structure has a sleeve 10
Insert the control rod guide tube 5 into the control rod guide tube 5.
is fixed to the sleeve 10 to constitute the framework of the fuel assembly 1. Further, the fuel rods 6 are inserted into the lattice space 9, and the fuel rods 6 are supported so as to be parallel to each other at regular intervals.

「発明が解決しようとする問題点」 ところで、従来の支持格子4は、燃料集合体を
構成する状態において、スリーブ10を装着した
部分の外側の強度が内側に対して弱いという欠点
があつた。
"Problems to be Solved by the Invention" By the way, the conventional support grid 4 had a drawback in that, when forming a fuel assembly, the outside strength of the part where the sleeve 10 was attached was weaker than the inside strength.

すなわち、スリーブ10を装着した部分の内側
は、スリーブ10を通して制御棒案内管5が配設
されており、制御棒案内管が補強部材となるため
強度が強くなり、外側は、制御棒案内管が無いた
め内側に比べて相対的に強度が弱くなる。
That is, on the inside of the part where the sleeve 10 is attached, the control rod guide tube 5 is arranged through the sleeve 10, and the control rod guide tube becomes a reinforcing member, so the strength is increased, and on the outside, the control rod guide tube is installed. Since there is no inner layer, the strength is relatively weak compared to the inner side.

スリーブ10の装着された部分の外側の強度を
補うには、ストラツプ8の板厚を厚くすればよい
が、そうすると、中性子吸収材を増やすことにな
つて原子炉稼働経済上望ましくないという問題が
生じる。
In order to compensate for the strength of the outside of the part where the sleeve 10 is attached, it is possible to increase the thickness of the strap 8, but this increases the amount of neutron absorbing material, which is undesirable from the economic point of view of reactor operation. .

本発明は、支持格子4において、スリーブ10
の装着された部分の外側の強度が弱いという欠点
を、全体のストラツプ8の板厚の増加を抑えてい
かにして改善するかを問題にしている。
The present invention provides a sleeve 10 in the support grid 4.
The problem is how to improve the weak strength of the outer part of the strap 8 by suppressing an increase in the thickness of the entire strap 8.

「問題点を解決するための手段」 この発明は、原子炉燃料集合体の支持格子にお
いて、装着されるスリーブの最外側部に位置する
ストラツプを基準として、その内側より外側のス
トラツプの板厚を厚くしたものである。
``Means for Solving the Problems'' This invention provides that, in a support grid of a nuclear reactor fuel assembly, the thickness of the straps on the outside is greater than the thickness of the straps located on the outermost side of the sleeve to be installed as a reference. It is made thicker.

「実施例」 第1図ないし第5図は、この発明の一実施例を
示す図である。第1図において、第8図の構成要
素と同一の要素には同一の符号を付し、その説明
を省略する。
Embodiment FIGS. 1 to 5 are diagrams showing an embodiment of the present invention. In FIG. 1, the same elements as those in FIG. 8 are given the same reference numerals, and their explanations will be omitted.

この第1図に示す支持格子11が第8図に示す
支持格子4と異なる点は、支持格子の内側と外側
とでストラツプの板厚が異なる点である。すなわ
ち、支持格子11は、支持格子11に装着された
スリーブ10の最外側部に位置するストラツプを
基準にして内側部12とこの内側部12よりスト
ラツプの板厚の厚い外側部13とを具備してなる
ものである。
The support grid 11 shown in FIG. 1 differs from the support grid 4 shown in FIG. 8 in that the thickness of the straps is different on the inside and outside of the support grid. That is, the support grid 11 includes an inner part 12 based on the outermost strap of the sleeve 10 attached to the support grid 11, and an outer part 13 having a thicker strap than the inner part 12. This is what happens.

内側部12は、第2図に示すように縦ストラツ
プ14と横ストラツプ15を用いて、従来例と同
様にして縦ストラツプ14と横ストラツプ15を
それぞれ縦横に組んで格子状に形成してなるもの
である。縦ストラツプ14及び横ストラツプ15
には、長手方向の両端部に長手方向に延びる板片
状の継手部16が形成されている。
The inner part 12 is formed by using vertical straps 14 and horizontal straps 15, and as shown in FIG. It is. Vertical strap 14 and horizontal strap 15
A plate-shaped joint portion 16 extending in the longitudinal direction is formed at both ends in the longitudinal direction.

外側部13は、第3図に示すように縦ストラツ
プ17と横ストラツプ18を用いて、従来例と同
様にして縦ストラツプ17と横ストラツプ18と
をそれぞれ縦横に組んで格子状に形成してなるも
のである。また、外側部13の内部には、開口部
19が形成されている。縦ストラツプ17及び横
ストラツプ18の長さの短い短ストラツプ20に
は、長手方向に延びる板片状の継手部21が形成
されている。
As shown in FIG. 3, the outer part 13 is formed by using vertical straps 17 and horizontal straps 18, and forming a lattice shape by assembling the vertical straps 17 and horizontal straps 18 vertically and horizontally, respectively, in the same manner as in the conventional example. It is something. Furthermore, an opening 19 is formed inside the outer portion 13 . A short strap 20 having a short length of the vertical strap 17 and the horizontal strap 18 is formed with a plate-shaped joint portion 21 extending in the longitudinal direction.

内側部12と外側部13は、第4図、第5図に
示すように、内側部12のストラツプと外側部1
3のストラツプとの厚さ方向の中心を一致させて
継手部16と継手部21とが組み合わされ、これ
らの継手部16と継手部21とをろう付等で結合
することにより連結されている。
The inner part 12 and the outer part 13 are connected to the strap of the inner part 12 and the outer part 1, as shown in FIGS.
The joint portion 16 and the joint portion 21 are combined with each other so that their centers in the thickness direction coincide with those of the strap No. 3, and the joint portion 16 and the joint portion 21 are connected by brazing or the like.

継手部16と継手部21とを組み合わせる第1
の方法は、第4図に示すように継手部16を継手
部21の側面と外側部13のストラツプのスリツ
ト7の間に挿入しこの継手部16を外側部13の
ストラツプの外側面に沿つて折り曲げ、継手部2
1を外側部13のストラツプの内側面に沿つて折
り曲げる方法である。第2の方法は、第5図に示
すように継手部16を継手部21の側面と外側部
13のストラツプのスリツト7の間に挿入する方
法である。
The first part that combines the joint part 16 and the joint part 21
As shown in FIG. 4, the joint part 16 is inserted between the side surface of the joint part 21 and the slit 7 of the strap of the outer part 13, and the joint part 16 is inserted along the outer surface of the strap of the outer part 13. Bending, joint part 2
1 along the inner surface of the strap of the outer part 13. The second method is to insert the joint part 16 between the side surface of the joint part 21 and the slit 7 of the strap of the outer part 13, as shown in FIG.

上記構成からなる支持格子11によれば、外側
部13のストラツプの板厚を内側部12より厚く
したから、支持格子11を燃料集合体1に組み込
んだ時に、内側部12に対して相対的に弱くなる
外側部13を補強することができ、全体のストラ
ツプの板厚を厚くすることなく支持格子11の全
体の強度を十分なものにすることができる。した
がつて、外側部13の補強に対してストラツプの
板厚の増加を最小限に抑えることができるので、
支持格子11の価格の上昇を最小限に抑えること
ができる。
According to the support grid 11 having the above structure, since the thickness of the straps of the outer part 13 is made thicker than that of the inner part 12, when the support grid 11 is assembled into the fuel assembly 1, The weakened outer portion 13 can be reinforced, and the overall strength of the support grid 11 can be made sufficient without increasing the thickness of the entire strap. Therefore, it is possible to minimize the increase in the thickness of the strap for reinforcing the outer part 13.
An increase in the price of the support grid 11 can be minimized.

「発明の効果」 この発明によれば、原子炉燃料集合体の支持格
子において、装着されるスリーブの最外側部に位
置するストラツプを基準としてその内側より外側
のストラツプの板厚を厚くしたから、支持格子を
燃料集合体に組込んだ時に支持格子の上記内側に
対して相対的に強度の弱くなる上記外側のストラ
ツプを補強することができ、全体のストラツプの
板厚を厚くすることなく支持格子の全体の強度を
十分なものにすることができる。したがつて、上
記外側のストラツプの補強に対してストラツプの
板厚の増加を最小限に抑えることができるので、
支持格子の価格の上昇を最小限に抑えることがで
きる。
"Effects of the Invention" According to the present invention, in the support grid of a nuclear reactor fuel assembly, the thickness of the outer strap is thicker than that of the inner strap, based on the strap located at the outermost part of the sleeve to be attached. When the support grid is assembled into a fuel assembly, it is possible to reinforce the outer straps, which have relatively weaker strength than the inner side of the support grid, without increasing the overall thickness of the support grid. can have sufficient overall strength. Therefore, it is possible to minimize the increase in the thickness of the strap for reinforcing the outer strap.
The increase in the price of the support grid can be minimized.

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

第1図はこの発明の一実施例として示した支持
格子の平面図、第2図は同支持格子の内側部を示
す斜視図、第3図は同支持格子の外側部を示す斜
視図、第4図、第5図は同支持格子の継手部の組
み合わせ方を示す説明図、第6図は燃料集合体を
示す正面図、第7図は支持格子を構成するストラ
ツプを示す正面図、第8図は従来の支持格子を示
す平面図である。 1……燃料集合体、4,11……支持格子、7
……スリツト、8……ストラツプ、9……格子空
間、10……スリーブ。
FIG. 1 is a plan view of a support grid shown as an embodiment of the present invention, FIG. 2 is a perspective view showing the inside part of the support grid, FIG. 3 is a perspective view showing the outside part of the support grid, and FIG. Figures 4 and 5 are explanatory diagrams showing how to combine the joints of the support grid, Figure 6 is a front view showing the fuel assembly, Figure 7 is a front view showing the straps forming the support grid, and Figure 8 The figure is a plan view showing a conventional support grid. 1... Fuel assembly, 4, 11... Support grid, 7
...slit, 8...strap, 9...lattice space, 10...sleeve.

Claims (1)

【特許請求の範囲】[Claims] 1 長方形状を有する薄板にその長手方向と直角
な方向に一定間隔ごとに多数の切込みを入れてス
リツトを形成してなるストラツプを多数用いて、
これらのストラツプの上記スリツトを互いに嵌め
合わせて縦横に組んで多数の格子空間を形成し、
これらの格子空間のいずれかと軸線を一致させて
円筒形のスリーブが装着される原子炉燃料集合体
の支持格子において、装着されるスリーブの最外
側部に位置するストラツプを基準として、その内
側より外側のストラツプの板厚を厚くしたことを
特徴とする原子炉燃料集合体の支持格子。
1 Using a large number of straps formed by forming slits by making a large number of cuts at regular intervals in a direction perpendicular to the longitudinal direction of a rectangular thin plate,
The above-mentioned slits of these straps are fitted into each other and assembled vertically and horizontally to form a large number of lattice spaces,
In the support grid of a reactor fuel assembly in which a cylindrical sleeve is mounted with its axis aligned with one of these grid spaces, the strap located at the outermost part of the sleeve to be mounted is used as a reference, and A support grid for a nuclear reactor fuel assembly characterized by having thicker straps.
JP61196778A 1986-08-22 1986-08-22 Support lattice for reactor fuel aggregate Granted JPS6352093A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61196778A JPS6352093A (en) 1986-08-22 1986-08-22 Support lattice for reactor fuel aggregate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61196778A JPS6352093A (en) 1986-08-22 1986-08-22 Support lattice for reactor fuel aggregate

Publications (2)

Publication Number Publication Date
JPS6352093A JPS6352093A (en) 1988-03-05
JPH0511873B2 true JPH0511873B2 (en) 1993-02-16

Family

ID=16363475

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61196778A Granted JPS6352093A (en) 1986-08-22 1986-08-22 Support lattice for reactor fuel aggregate

Country Status (1)

Country Link
JP (1) JPS6352093A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR102460092B1 (en) * 2020-08-28 2022-10-31 한전원자력연료 주식회사 Inconel spacer grid of a nuclear fuel assembly

Also Published As

Publication number Publication date
JPS6352093A (en) 1988-03-05

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