JPH01189593A - Fuel support for fast breeder reactor - Google Patents

Fuel support for fast breeder reactor

Info

Publication number
JPH01189593A
JPH01189593A JP63012696A JP1269688A JPH01189593A JP H01189593 A JPH01189593 A JP H01189593A JP 63012696 A JP63012696 A JP 63012696A JP 1269688 A JP1269688 A JP 1269688A JP H01189593 A JPH01189593 A JP H01189593A
Authority
JP
Japan
Prior art keywords
arm
operating arm
fuel assembly
connecting pipe
connection pipe
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.)
Pending
Application number
JP63012696A
Other languages
Japanese (ja)
Inventor
Yasuhiko Aida
安彦 相田
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP63012696A priority Critical patent/JPH01189593A/en
Publication of JPH01189593A publication Critical patent/JPH01189593A/en
Pending 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)

Abstract

PURPOSE:To intend an improvement of safety, by making a hook placed at an end of a working arm so as to fit with a groove dug to an entrance nozzle when a fuel assembly is placed completely at its final position, as the entrance nozzle is being inserted into a connection pipe. CONSTITUTION:When an entrance nozzle 4 is inserted into a connection pipe 3, a lower part of a working arm 5 is pushed downwardly and the arm 5 is made to rotate around a rotating axis 6. At a situation where a fuel assembly is placed completely at its final position, a hook 7 placed at an end of the arm 5 is fitted into a groove 8 of the nozzle 4. An axis 6 is supported by an axis hole 9 drilled into a connection pipe 3, and by using a material which has a higher thermal expansion rate than that of a material for the connection pipe 3, as the material for the axis 6, the axis 6 and the axis hole 9 is close fitted during a nuclear reactor is operated (at a higher temperature condition) therewith a rotation of the arm 5 is restricted. Consequently, an upward movement of the fuel assembly is restricted. Also, the arm 5 and a stopper 10 which is fixed to the connection pipe 3 are connected with a spring mechanism 11, and during a refueling (at a lower temperature condition), a righting force works on the arm 5, the hook 7 is unlatched from the groove 8 and the fuel assembly can be withdrawn.

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は、高速増殖炉の燃料支持装置に関する。[Detailed description of the invention] [Purpose of the invention] (Industrial application field) The present invention relates to a fuel support device for a fast breeder reactor.

(従来の技術) 高速増殖炉における炉心は、炉心槽内に多数の六角形状
の燃料集合体が配置されτいる。第6図に示す様に、各
燃料集合体1は、炉心支持板2に固定された連結管3の
中に、燃料集合体下部のエントランスノズル4が挿入さ
れることによシ支持されており、上下方向には全く拘束
されていない。
(Prior Art) A reactor core in a fast breeder reactor has a large number of hexagonal fuel assemblies arranged in a core barrel. As shown in FIG. 6, each fuel assembly 1 is supported by an entrance nozzle 4 at the bottom of the fuel assembly inserted into a connecting pipe 3 fixed to a core support plate 2. , is not constrained in the vertical direction at all.

(発明が解決しようとする課題) 上記の様な支持方法においては、炉心に上下地震動が加
わると、燃料集合体は上下に振動あるいは浮き上る可能
性がある。また浮き上った後。
(Problems to be Solved by the Invention) In the support method described above, when vertical seismic motion is applied to the reactor core, the fuel assembly may vibrate or float up and down. After surfacing again.

落下する時には、炉心支持板に衝撃荷重が加わることに
なる。
When falling, an impact load will be applied to the core support plate.

本発明は、このような事情に鑑みてなされたもので、地
1時に燃料集合体が上下に振動することおよび浮き上る
ことを防止し、炉心支持板に加わる衝撃荷重を緩和する
ことによシ、安全性の高い原子炉を提供することを目的
とする。
The present invention has been made in view of the above circumstances, and prevents the fuel assembly from vertically vibrating and floating when it is grounded, and reduces the shock load applied to the core support plate. The aim is to provide highly safe nuclear reactors.

〔発明の構成〕[Structure of the invention]

C11題を解決するための手段) 本発明では、燃料集合体の下部にあるエントランスノズ
ルを連結管に挿入し、支持する際に、エントランスノズ
ルの下端に押されて回転する作動アームを連結管側壁に
設置し、燃料集合体が完全に着座した状態では、作動ア
ーム先端にある爪が、エントランスノズルに設けた溝に
はま)込む構造とすることにより、燃料集合体の上方向
への動きを拘束している。
Means for Solving Problem C11) In the present invention, when the entrance nozzle at the lower part of the fuel assembly is inserted into the connecting pipe and supported, the operating arm, which is pushed by the lower end of the entrance nozzle and rotates, is attached to the side wall of the connecting pipe. When the fuel assembly is installed in I'm restrained.

(作 用) 本発明によれば、原子炉運転時(高温時)には1作動ア
ームの回転中心である回転軸が熱膨張によシ連結管の軸
受穴との間で締まシはじめとなシ作動アームの回転運動
を拘束することになる。
(Function) According to the present invention, during reactor operation (at high temperatures), the rotating shaft, which is the center of rotation of one operating arm, tightens with the bearing hole of the connecting pipe due to thermal expansion. This restricts the rotational movement of the operating arm.

作動アーム先端の爪でエントランスノズルを動きを押え
ていることから、燃料集合体の上方向への動きを拘束す
ることが出来る。
Since the movement of the entrance nozzle is restrained by the claw at the tip of the operating arm, upward movement of the fuel assembly can be restrained.

また、作動アームと連結管に固定されたストッパー間は
、ばね機構で結合されており、燃料交換時(低温時)に
は、回転軸は回転自由であシ、燃料集合体の上方向への
移動と連動して5作動アームには復元力が得られ作動ア
ーム先端の爪は溝からはずれる。従って低温時には、燃
料集合体を連結管から自由に引き抜くことが出来る。
In addition, the actuating arm and the stopper fixed to the connecting pipe are connected by a spring mechanism, so that during fuel exchange (at low temperatures), the rotating shaft is free to rotate, and the fuel assembly is moved upward. In conjunction with the movement, a restoring force is obtained in the operating arm 5, and the claw at the tip of the operating arm is removed from the groove. Therefore, at low temperatures, the fuel assembly can be freely pulled out from the connecting pipe.

(実施例) 以下1本発明による実施例を図面により詳細に説明する
。第1図乃至第5図に本発明の実施例を縦断面図および
部分的な横断面にて示す、第1図および第2図はエント
ランスノズル4が連結管3に挿入されている途中でエン
トランスノズル4の先端が作動アーム5に接触する前の
状態を示している。さらにエントランスノズル4が挿入
されると作動アーム5の下部を上から押すことになシ、
作動アーム5は回転軸6を中心に回転運動を始める。そ
して第3図および第4図に示す様に、燃料集合体1が完
全に着座した状態では作動アーム5の先端にある爪7が
エントランスノズル4に設けた溝8にはまり込む構造と
なっている。
(Example) Hereinafter, an example according to the present invention will be described in detail with reference to the drawings. 1 to 5 show an embodiment of the present invention in longitudinal section and partial cross section. FIGS. 1 and 2 show the entrance nozzle 4 inserted into the connecting pipe 3. The state before the tip of the nozzle 4 contacts the actuating arm 5 is shown. Furthermore, when the entrance nozzle 4 is inserted, it is necessary to press the lower part of the operating arm 5 from above.
The actuating arm 5 begins to rotate around the rotation axis 6. As shown in FIGS. 3 and 4, when the fuel assembly 1 is completely seated, the claw 7 at the tip of the operating arm 5 fits into the groove 8 provided in the entrance nozzle 4. .

回転軸6は、連結管3に設けた軸受穴9によシ支持され
ており、回転軸の材料を連結管に比べ、熱膨張率の高い
ものとすることによ#)、原子炉運転時(高温時)には
回転軸6と軸受穴9の間は、締まりばめとなシ1作動ア
ーム5の回転運動は拘束される。従って燃料集合体の上
方向への動きは拘束される。さらに作動アーム5と連結
管3に固定されたストッパーlOの間はばね機構11に
よシ結合されておシ燃料交換時(低温時)には回転軸6
が回転自由であるから作動アーム5には復元力が働き、
エントランスノズル4の上方向への移動して爪7は、溝
8からはずれ、燃料集合体を引き抜くことが出来る。
The rotating shaft 6 is supported by a bearing hole 9 provided in the connecting pipe 3, and is made of a material with a higher coefficient of thermal expansion than that of the connecting pipe. (At high temperatures), there is an interference fit between the rotating shaft 6 and the bearing hole 9, and the rotational movement of the actuating arm 5 is restricted. Therefore, upward movement of the fuel assembly is restricted. Furthermore, a spring mechanism 11 connects between the actuating arm 5 and a stopper lO fixed to the connecting pipe 3.
Since it is free to rotate, a restoring force acts on the actuating arm 5,
As the entrance nozzle 4 moves upward, the pawl 7 disengages from the groove 8 and the fuel assembly can be pulled out.

以上、説明した作動アーム5及び溝8の周方向配置、数
は任意である。また燃料集合体を装荷する際に、水平角
度に自由度を持たせたい場合は、溝8の幅を大きくして
もかまわない。
The circumferential arrangement and number of the operating arms 5 and grooves 8 described above are arbitrary. Furthermore, if it is desired to have a degree of freedom in the horizontal angle when loading the fuel assembly, the width of the groove 8 may be increased.

第5図には、他の実施例を示す、基本的な構成・原理は
上記の実施例と同じであるが、異なる所は、作動アーム
とストッパーを結合するばね機構に替えて1作動アーム
5の先端、爪7の反対側にカウンターウェイト12を取
付けたことである。
FIG. 5 shows another embodiment. The basic structure and principle are the same as the above embodiment, but the difference is that the spring mechanism connecting the operating arm and the stopper is replaced with one operating arm 5. A counterweight 12 is attached to the opposite end of the claw 7.

これにより、作動アーム5が直立した場合でも、作動ア
ーム全体の重心は常に回転軸を通る鉛直線よシ外側にあ
る状態が作れる。従って低温時に作動アームが回転自由
の場合、作動アームには重力による復元力が働きエント
ランスノズル4の上方向への移動と連動して爪7は$8
からはずれる。
Thereby, even when the actuating arm 5 stands upright, a state can be created in which the center of gravity of the entire actuating arm is always outside the vertical line passing through the rotation axis. Therefore, when the operating arm is free to rotate at low temperatures, a restoring force due to gravity acts on the operating arm, and in conjunction with the upward movement of the entrance nozzle 4, the claw 7
It deviates from the

〔発明の効果〕〔Effect of the invention〕

本発明の高速壇殖炉の燃料支持装置によれば、原子炉運
転中(高温時)には、燃料集合体は上下方向の動きを拘
束されておシ、炉心に上下地震動が加わっても、燃料集
合体の上下振動および浮き上りを防止することが出来、
比較的簡単な構造で上下方向の耐震性を満足した安全性
の高い炉心が成立する。
According to the fuel support device for a high-speed bed reactor of the present invention, the fuel assembly is restrained from vertical movement during reactor operation (at high temperatures), and even if vertical seismic motion is applied to the reactor core, Vertical vibration and lifting of the fuel assembly can be prevented,
A highly safe core with a relatively simple structure that satisfies earthquake resistance in the vertical direction can be created.

また燃料交換時(低温時)には、上下方向の拘束が解除
され、燃料集合体を炉心から自由に引き抜くことが出来
る。
Furthermore, during fuel exchange (at low temperatures), the vertical restraints are released and the fuel assembly can be freely pulled out from the core.

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

第1図は本発明の一実施例を示す要部縦断面図第2図は
第1図中のAA矢視図、第3図は本発明の一実施例の動
作状態を示す要部縦断面図、第4図は第3図中のAA矢
視図、第5図は本発明による他の実施例を縦断面図、第
6図は従来の燃料集合体の支持状態を示す断面図である
。 1・・・燃料集合体、2・・・炉心支持板、3・・・連
結管。 4・・・エントランスノズル、5・・・作動y−,t−
,h6・・・回転軸%7・・・爪、8・・・溝% 9・
・・軸受穴、10・・・ストッパー、11・・・ばね機
構、12・・・カウンターウェイト。 第  1  図 i2  図 7 第  5  図 第  6  図
FIG. 1 is a vertical cross-sectional view of a main part showing an embodiment of the present invention. FIG. 2 is a view taken along arrow AA in FIG. 1. FIG. 4 is a view taken along the arrow AA in FIG. 3, FIG. 5 is a longitudinal cross-sectional view of another embodiment of the present invention, and FIG. 6 is a cross-sectional view showing the supporting state of a conventional fuel assembly. . DESCRIPTION OF SYMBOLS 1... Fuel assembly, 2... Core support plate, 3... Connecting pipe. 4... Entrance nozzle, 5... Operation y-, t-
, h6... Rotating shaft %7... Claw, 8... Groove% 9.
...Bearing hole, 10...Stopper, 11...Spring mechanism, 12...Counterweight. Figure 1 Figure i2 Figure 7 Figure 5 Figure 6

Claims (4)

【特許請求の範囲】[Claims] (1)高速増殖炉の燃料集合体を下端で支持する連結管
において、エントランスノズルが連結管内に挿入する際
に、エントランスノズルに押されて回転する作動アーム
を設置し、燃料集合体が完全に着座した状態では、作動
アーム先端にある爪が、エントランスノズルに設けた溝
にはまり込む構造としたことを特徴とする高速増殖炉の
燃料支持装置。
(1) In the connecting pipe that supports the fuel assembly of a fast breeder reactor at its lower end, an operating arm is installed that is pushed and rotated by the entrance nozzle when the entrance nozzle is inserted into the connecting pipe, so that the fuel assembly is completely A fuel support device for a fast breeder reactor, characterized in that, in a seated state, a claw at the tip of an operating arm fits into a groove provided in an entrance nozzle.
(2)作動アームの回転中心である回転軸の材料を、連
結管に比べ熱膨張率の高いものとすることにより、原子
炉運転時(高温時)には、回転軸と連結管側の軸受穴と
の間が締りばめとなり、作動アームの回転運動が拘束さ
れることを特徴とする請求項1記載の高速増殖炉の燃料
支持装置。
(2) By making the material of the rotating shaft, which is the center of rotation of the operating arm, a material with a higher coefficient of thermal expansion than that of the connecting pipe, during reactor operation (at high temperatures), the bearings on the rotating shaft and connecting pipe side 2. The fuel support device for a fast breeder reactor according to claim 1, wherein the operating arm is tightly fitted to the hole and rotational movement of the operating arm is restricted.
(3)作動アームと連結管に固定されたストッパーの間
をばね機構で結合することにより、作動アームに復元力
が得られる構造としたことを特徴とする請求項1記載の
高速増殖炉の燃料支持装置。
(3) The fuel for the fast breeder reactor according to claim 1, characterized in that the operating arm has a structure in which a restoring force is obtained by coupling the operating arm and the stopper fixed to the connecting pipe with a spring mechanism. Support device.
(4)作動アームにカウンターウェイトを付加すること
により、作動アームに重力による復元力が働く構造した
ことを特徴とする請求項1記載の高速増殖炉の燃料支持
装置。
(4) The fuel support system for a fast breeder reactor according to claim 1, wherein a restoring force due to gravity is applied to the operating arm by adding a counterweight to the operating arm.
JP63012696A 1988-01-25 1988-01-25 Fuel support for fast breeder reactor Pending JPH01189593A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63012696A JPH01189593A (en) 1988-01-25 1988-01-25 Fuel support for fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63012696A JPH01189593A (en) 1988-01-25 1988-01-25 Fuel support for fast breeder reactor

Publications (1)

Publication Number Publication Date
JPH01189593A true JPH01189593A (en) 1989-07-28

Family

ID=11812546

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63012696A Pending JPH01189593A (en) 1988-01-25 1988-01-25 Fuel support for fast breeder reactor

Country Status (1)

Country Link
JP (1) JPH01189593A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2020176911A (en) * 2019-04-18 2020-10-29 日立Geニュークリア・エナジー株式会社 Fuel assembly

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2020176911A (en) * 2019-04-18 2020-10-29 日立Geニュークリア・エナジー株式会社 Fuel assembly

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