JPH02129596A - Fuel exchanger for fast breeder - Google Patents

Fuel exchanger for fast breeder

Info

Publication number
JPH02129596A
JPH02129596A JP63284156A JP28415688A JPH02129596A JP H02129596 A JPH02129596 A JP H02129596A JP 63284156 A JP63284156 A JP 63284156A JP 28415688 A JP28415688 A JP 28415688A JP H02129596 A JPH02129596 A JP H02129596A
Authority
JP
Japan
Prior art keywords
fuel
gripper
orientation
reactor
main body
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
JP63284156A
Other languages
Japanese (ja)
Other versions
JP2559263B2 (en
Inventor
Hiroshi Ozaki
博 尾崎
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.)
Fuji Electric Co Ltd
Original Assignee
Fuji Electric 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 Fuji Electric Co Ltd filed Critical Fuji Electric Co Ltd
Priority to JP63284156A priority Critical patent/JP2559263B2/en
Publication of JPH02129596A publication Critical patent/JPH02129596A/en
Application granted granted Critical
Publication of JP2559263B2 publication Critical patent/JP2559263B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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)
  • Length Measuring Devices Characterised By Use Of Acoustic Means (AREA)

Abstract

PURPOSE:To set fuel at a specific position by providing a fuel orientation device which drives and rotates a gripper gripping the fuel from outside a nuclear reactor and a fuel discriminating device which discriminates the discrimination pattern of a fuel top part. CONSTITUTION:An orientation rod 8 is connected to the gripper 4 from above a main body barrel 1 while a pantagraph arm 3 is folded. The fuel is positioned at the specific position by rotating the gripper 4 by a fuel rotary driving mechanism 6. The fuel discriminating device 9 is fitted horizontally to the lower end of the main body barrel 1 opposite the discrimination pattern of the fuel 5, and an ultrasonic wave transmitter and a receiver are provided. The gripper 4 engages the fuel 5 and can move up and down, and an ultrasonic wave is sent to above the fuel 5 from the device 9 toward an annular discrimination pattern. Its reflected wave is received to discriminate the kind of the fuel 5. The gripper 4 grips the fuel 5 in a hold-down tube 2 and a rod 8 is lowered to position the fuel 5 in a specific direction by a fuel rotating mechanism 6.

Description

【発明の詳細な説明】[Detailed description of the invention] 【産業上の利用分野】[Industrial application field]

この発明は、液体金属を冷却材とする高速増殖炉の燃料
を交換する燃料交換機に関する。
The present invention relates to a fuel exchanger for exchanging fuel in a fast breeder reactor that uses liquid metal as a coolant.

【従来の技術】[Conventional technology]

第4図は従来例による高速増殖炉用燃料交換機の断面図
である。第4図において、本体胴l側におけるアーム伸
縮駆動機構のボールねしに螺合したボス12とホールド
ダウンチューブ2との間に跨がって架設されたパンタグ
ラフアーム3は、長手方向の中央部に段違いとなる段差
を形成したアーム板と、それぞれ互いに反対側に張り出
したアーム板両端部にはフランジ部が形成されている。 グリッパ4で燃料5をつかんでホールドダウンチューブ
2に収めている。6は燃料回転駆動機構。 7はグリッパ昇降駆動装置である。 かかる構成によりパンタグラフアーム3を水平方向に伸
ばして前記ホールドダウンチューブ2を本体胴1の側方
へ引き出した燃料交換位置からパンタグラフアーム3を
折り畳むと、本体胴1側ではアーム伸縮駆動機構がパン
タグラフアームのU字溝内に納まり、一方のパンタグラ
フアーム3はフランジ部のU字溝に納まるようになる。 高速増殖炉の燃料は、六角形断面の長尺構造であり、炉
心は蜂の巣状に燃料が互いにガイドされながら構成され
ている。 燃料交換機によって燃料を炉心に挿入する場合、燃料の
方位が合うように全ての燃料の上下部に王冠状の斜めの
突起部を備え、燃料を炉心に押し込むにつれて燃料が所
定の方位に位置決めされる(これを燃料のセルフオリエ
ンテーションという)構造となっている。 また、各炉心構成要素(燃料集合体、制御棒集合体等)
の下部エントランスノズル部とこのエントランスノズル
が挿入される炉心下部の連結部の形状を炉心構成要素の
種類毎に異なる形状としておくことにより、炉心内に誤
った炉心構成要素を装着した場合には、挿入を完全に行
うことができなくなり、挿入状態から炉心構成要素の種
類が的確か否かを判断することができる。
FIG. 4 is a sectional view of a conventional refueling machine for a fast breeder reactor. In FIG. 4, the pantograph arm 3, which is installed across the hold-down tube 2 and the boss 12 screwed into the ball screw of the arm telescoping drive mechanism on the main body trunk l side, is located at the central portion in the longitudinal direction. The arm plate has a step formed thereon, and flanges are formed at both ends of the arm plate, which project toward opposite sides. A gripper 4 grips fuel 5 and stores it in a hold down tube 2. 6 is a fuel rotation drive mechanism. 7 is a gripper lifting/lowering drive device. With this configuration, when the pantograph arm 3 is folded from the fuel exchange position where the pantograph arm 3 is extended horizontally and the hold-down tube 2 is pulled out to the side of the main body 1, the arm extension/contraction drive mechanism on the main body 1 side One pantograph arm 3 is fitted into the U-shaped groove of the flange. The fuel of a fast breeder reactor has an elongated structure with a hexagonal cross section, and the reactor core is configured such that the fuel is guided to each other in a honeycomb shape. When inserting fuel into the reactor core using a refueling machine, all fuels are provided with crown-shaped diagonal protrusions on the top and bottom of the fuel so that the orientation of the fuel matches, and as the fuel is pushed into the core, the fuel is positioned in a predetermined orientation. (This is called fuel self-orientation). In addition, each core component (fuel assembly, control rod assembly, etc.)
By making the shapes of the lower entrance nozzle part and the connecting part of the lower part of the core into which this entrance nozzle is inserted different for each type of core component, if the wrong core component is installed in the core, It becomes impossible to complete the insertion, and it is possible to judge from the inserted state whether or not the type of core component is correct.

【発明が解決しようとする課題】[Problem to be solved by the invention]

従来の燃料自身のセルフオリエンテーションあるいは炉
心下部の連結部構造による炉心構成要素の確認方法は、
比較的小出力の原子炉用として実施されており、これを
大型の原子炉に適用すると以下の問題がある。 (1)大型炉では炉心も大型化し、燃料の寿命を伸ばす
要求も大きくなることから炉心側の燃料を挿入する六角
形の穴の変形(横方向、高さ方向のばらつき等)が相対
的に大きくなり、このような場合燃料のセルフオリエン
テーションによる燃料の方位設定を期待してもうまくい
かないことが多く、その結果燃料交換期間の増加あるい
はプラント利用率低下につながる。 (2)大型炉では1回の燃料交換期間に交換する炉心構
成要素の本数が多く、安全上の理由から炉心構成要素の
誤取扱の検知に対する要求は大きくなっている。 この発明は、燃料をつかんだグリッパを原子炉の外から
回転駆動する燃料オリエンテーション装置と、燃料の頂
部に刻まれた識別パターンを識別する燃料識別装置とを
備えた燃料交換機を提供することを目的とする。
The conventional method of confirming core components using self-orientation of the fuel itself or the joint structure at the bottom of the core is as follows:
This method has been implemented for relatively small-power nuclear reactors, and when applied to large-scale nuclear reactors, the following problems arise. (1) In large reactors, the core becomes larger and the demand for extending the fuel life increases, so the deformation (lateral and height variations, etc.) of the hexagonal hole in the core side into which the fuel is inserted becomes relatively large. In such cases, even if we hope to set the direction of the fuel by fuel self-orientation, it is often unsuccessful, resulting in an increase in the refueling period or a decrease in plant utilization. (2) In large reactors, a large number of core components are replaced during one refueling period, and for safety reasons, there is a growing demand for detection of mishandling of core components. An object of the present invention is to provide a fuel exchange machine equipped with a fuel orientation device that rotationally drives a gripper that grips fuel from outside the reactor, and a fuel identification device that identifies an identification pattern engraved on the top of the fuel. shall be.

【課題を解決するための手段】[Means to solve the problem]

上記目的は、燃料のつかみ、はなしを行うグリッパに着
脱自在に構成されたオリエンテーションロッド及びこの
オリエンテーションロッドを原子炉外から回転操作でき
る燃料回転駆動機構からなる燃料オリエンテーション装
置と、前記燃料の頂部に刻まれた環状の溝の組合せから
なる識別パターンに対向するように、本体胴の下端に水
平方向に取り付けられ、超音波の受発信装置からなる燃
料識別装置とを備えた高速増殖炉用燃料交換機によって
達成される。
The above object is to provide a fuel orientation device consisting of an orientation rod that is detachably attached to a gripper that grips and releases fuel, a fuel rotation drive mechanism that can rotate this orientation rod from outside the reactor, and a fuel orientation device that is engraved on the top of the fuel. A fuel exchanger for a fast breeder reactor is installed horizontally at the lower end of the main body so as to face an identification pattern consisting of a combination of annular grooves, and is equipped with a fuel identification device consisting of an ultrasonic receiving and transmitting device. achieved.

【作 用】[For use]

燃料のつかみ、はなしを行うグリッパを原子炉外から回
転操作できる燃料オリエンテーション装置により、パン
タグラフアームを畳んだ状態で燃料の回転方位を設定で
き、かつ本体胴の下方に水平方向に取り付けた燃料識別
装置により燃料交換機がつかんでいる炉心構成要素の種
類を識別することができる。
A fuel orientation device that can rotate the gripper that grips and releases fuel from outside the reactor allows the rotation direction of the fuel to be set with the pantograph arm folded, and a fuel identification device that is installed horizontally below the main body shell. can identify the type of core component that the refueling machine is grasping.

【実施例】【Example】

以下図面に基づいてこの発明の詳細な説明する。第1図
はこの発明の実施例による高速増殖炉用燃料交換機の構
造を示す断面図、第2図は第1図の燃料交換機の燃料識
別装置による燃料識別状態を示す外形図、第3図は第1
図の燃料交換機の燃料回転駆動部の断面図である。第1
図、第2図。 第3図において第4図と同じ部位は同じ番号を付しであ
る。 第1図において、本体胴1側におけるアーム伸縮駆動機
構のボールねじに螺合したボス12とホールドダウンチ
ューブ2との間に跨がって架設されたパンタグラフアー
ム3は、長手方向の中央部に段違いとなる段差を形成し
たアーム板と、それぞれ互いに反対側に張り出したアー
ム板両端部にはフランジ部が形成されている。 かかる構成によりパンタグラフアーム3を水平方向に伸
ばして前記ホールドダウンチューブ2を本体胴1の側方
へ引き出した燃料交換位置からパンタグラフアーム3を
折り畳むと、本体胴1側ではアーム伸縮駆動機構がパン
タグラフアームのU字溝内に納まり、一方のパンタグラ
フアーム3はフランジ部のU字溝に納まるようになる。 第1図のごとくパンタグラフアーム3を畳んだ状態で本
体胴1の上部からオリエンテーションロッド8がグリッ
パ4に接続され、燃料交換機上端の燃料回転駆動機構6
でグリッパ4を回転することにり燃料5を所定の方位に
位置決めできる。前記オリエンテーションロツド8及び
燃料回転駆動機構6を総称して燃料オリエンテーション
装置11という。 第1図及び第2図において、燃料識別装置9は本体胴1
の下端に燃料5の識別パターン10に対向するように水
平方向に取り付けられ、超音波発信装置及び受信装置を
備えている。グリッパ4は、燃料5と係合していて、矢
印Aの方向に上下され、燃料5の上部には環状の溝の組
合せからなる識別パターンが刻まれていて、この識別パ
ターン10に向かって前記燃料識別装置9から超音波を
発信し、反射波を受信して燃料5の種類を識別する。 第3図において、ホールドダウンチューブ2内でグリッ
パ4は燃料5をつかみ、オリエンテーションロッド8を
下降させてこのオリエンテーションロッド8を前記グリ
ッパ4と係合させ燃料回転駆動機構6によって燃料5を
所定の方位に位置決めする。 グリッパ4は、グリッパ昇降駆動装置7によって昇降さ
せる。
The present invention will be described in detail below based on the drawings. FIG. 1 is a sectional view showing the structure of a fast breeder reactor refueling machine according to an embodiment of the present invention, FIG. 2 is an outline view showing the state of fuel identification by the fuel identification device of the refueling machine of FIG. 1, and FIG. 1st
FIG. 3 is a cross-sectional view of the fuel rotation drive section of the fuel exchanger shown in the figure. 1st
Figure, Figure 2. In FIG. 3, the same parts as in FIG. 4 are given the same numbers. In FIG. 1, the pantograph arm 3 is installed across the hold-down tube 2 and the boss 12 screwed into the ball screw of the arm telescopic drive mechanism on the body trunk 1 side. Flange portions are formed on the arm plate having different steps and on both ends of the arm plate projecting to opposite sides. With this configuration, when the pantograph arm 3 is folded from the fuel exchange position where the pantograph arm 3 is extended horizontally and the hold-down tube 2 is pulled out to the side of the main body 1, the arm extension/contraction drive mechanism on the main body 1 side One pantograph arm 3 is fitted into the U-shaped groove of the flange. As shown in FIG. 1, with the pantograph arm 3 folded, an orientation rod 8 is connected to the gripper 4 from the upper part of the body trunk 1, and a fuel rotation drive mechanism 6 at the upper end of the fuel exchanger
By rotating the gripper 4, the fuel 5 can be positioned in a predetermined direction. The orientation rod 8 and the fuel rotation drive mechanism 6 are collectively referred to as a fuel orientation device 11. 1 and 2, the fuel identification device 9 is
It is attached horizontally to the lower end of the fuel 5 so as to face the identification pattern 10 of the fuel 5, and is equipped with an ultrasonic transmitting device and a receiving device. The gripper 4 is engaged with the fuel 5 and is moved up and down in the direction of the arrow A. The upper part of the fuel 5 is engraved with an identification pattern consisting of a combination of annular grooves, and the gripper 4 is engaged with the fuel 5 and is engraved with an identification pattern consisting of a combination of annular grooves. The fuel identification device 9 emits ultrasonic waves and receives reflected waves to identify the type of fuel 5. In FIG. 3, the gripper 4 grips the fuel 5 within the hold-down tube 2, lowers the orientation rod 8, engages the orientation rod 8 with the gripper 4, and directs the fuel 5 in a predetermined direction by the fuel rotation drive mechanism 6. position. The gripper 4 is raised and lowered by a gripper raising and lowering drive device 7.

【発明の効果】【Effect of the invention】

この発明によれば、グリッパを原子炉外から回転操作で
きる燃料オリエンテーション装置を備えたので、グリッ
パをつかんでいる燃料を所定の方位に設定することがで
きる。 さらに、零体動の下端に水平方向に取り付けられ超音波
の受発信機からなる燃料識別装置を備えたので、燃料頂
部に刻まれたリング状の溝の組合せからなる識別パター
ンを識別して交換すべき燃料の種類を確認することがで
きる。
According to this invention, since the fuel orientation device that can rotate the gripper from outside the reactor is provided, the fuel gripping the gripper can be set in a predetermined orientation. In addition, a fuel identification device consisting of an ultrasonic receiver and transmitter is attached horizontally to the lower end of the zero body motion, so the identification pattern consisting of a combination of ring-shaped grooves carved into the top of the fuel can be identified and replaced. You can check the type of fuel that should be used.

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

第1図はこの発明の実施例による高速増殖炉用燃料交換
機の断面図、第2図は第1図の高速増殖炉用燃料交換機
の燃料識別装置により燃料を識別している状態を示す図
、第3図は第1図における燃料回転機構部の断面図、第
4図は従来例による高速増殖炉用燃料交換機の断面図で
ある。 1:本体胴、2:ホールドダウンチューブ、3:パンタ
グラフアーム、4ニゲリツパ、5:燃料、6:燃料回転
駆動機構、7:グリッパ昇降駆動装置、8:オリエンテ
ーションロッド、9:燃料識別装置、lO:識別パター
ン、11:燃料オリエンテーション装置。 第1図 第 図 第 図
FIG. 1 is a sectional view of a fast breeder reactor refueling machine according to an embodiment of the present invention, and FIG. 2 is a diagram showing a state in which fuel is identified by the fuel identification device of the fast breeder reactor refueling machine of FIG. 1. FIG. 3 is a sectional view of the fuel rotation mechanism in FIG. 1, and FIG. 4 is a sectional view of a conventional fast breeder reactor refueling machine. 1: Main body trunk, 2: Hold down tube, 3: Pantograph arm, 4 Nigelippa, 5: Fuel, 6: Fuel rotation drive mechanism, 7: Gripper lifting/lowering drive device, 8: Orientation rod, 9: Fuel identification device, lO: Identification pattern, 11: Fuel orientation device. Figure 1 Figure 1

Claims (1)

【特許請求の範囲】[Claims] 1)高速増殖炉の原子炉容器に据え付けて炉心との間で
燃料交換を行うパンタグラフ式燃料交換機であつて、燃
料のつかみ、はなしを行うグリッパに着脱自在に配置さ
れたオリエンテーションロッド及びこのオリエンテーシ
ョンロッドを原子炉外から回転操作できる燃料回転駆動
機構からなる燃料オリエンテーション装置と、前記燃料
の頂部に刻まれた環状の溝の組合せからなる識別パター
ンに対向するように、本体胴の下端に水平方向に取り付
けられ、超音波の受発信装置からなる燃料識別装置とを
備えたことを特徴とする高速増殖炉用燃料交換機。
1) A pantograph type fuel exchanger installed in the reactor vessel of a fast breeder reactor to exchange fuel with the reactor core, and an orientation rod that is removably arranged on a gripper that grips and releases fuel, and this orientation rod. A fuel orientation device consisting of a fuel rotation drive mechanism that can be rotated from outside the reactor, and a fuel orientation device that is horizontally attached to the lower end of the main body so as to face an identification pattern consisting of a combination of annular grooves cut into the top of the fuel. 1. A fuel exchanger for a fast breeder reactor, characterized in that it is attached to a fuel identification device comprising an ultrasonic receiving and transmitting device.
JP63284156A 1988-11-10 1988-11-10 Refueling machine for fast breeder reactor Expired - Lifetime JP2559263B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63284156A JP2559263B2 (en) 1988-11-10 1988-11-10 Refueling machine for fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63284156A JP2559263B2 (en) 1988-11-10 1988-11-10 Refueling machine for fast breeder reactor

Publications (2)

Publication Number Publication Date
JPH02129596A true JPH02129596A (en) 1990-05-17
JP2559263B2 JP2559263B2 (en) 1996-12-04

Family

ID=17674904

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63284156A Expired - Lifetime JP2559263B2 (en) 1988-11-10 1988-11-10 Refueling machine for fast breeder reactor

Country Status (1)

Country Link
JP (1) JP2559263B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20090129527A1 (en) * 2007-11-19 2009-05-21 Korea Atomic Energy Research Institute And Korea Hydro & Nuclear Power Co., Ltd. Refueling apparatus for sodium-cooled fast reactor and method for the same

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5314293A (en) * 1976-07-23 1978-02-08 Toshiba Corp Nuclear fuel exchanging apparatus
JPS5979192A (en) * 1982-10-28 1984-05-08 株式会社東芝 Fuel discriminating device

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5314293A (en) * 1976-07-23 1978-02-08 Toshiba Corp Nuclear fuel exchanging apparatus
JPS5979192A (en) * 1982-10-28 1984-05-08 株式会社東芝 Fuel discriminating device

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20090129527A1 (en) * 2007-11-19 2009-05-21 Korea Atomic Energy Research Institute And Korea Hydro & Nuclear Power Co., Ltd. Refueling apparatus for sodium-cooled fast reactor and method for the same
KR100905375B1 (en) * 2007-11-19 2009-07-01 한국원자력연구원 Nuclear Fuel Exchange System and Fuel Exchange Method
US8542791B2 (en) 2007-11-19 2013-09-24 Korea Atomic Energy Research Institute Refueling apparatus for sodium-cooled fast reactor and method for the same

Also Published As

Publication number Publication date
JP2559263B2 (en) 1996-12-04

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