JPH0584879B2 - - Google Patents

Info

Publication number
JPH0584879B2
JPH0584879B2 JP61297891A JP29789186A JPH0584879B2 JP H0584879 B2 JPH0584879 B2 JP H0584879B2 JP 61297891 A JP61297891 A JP 61297891A JP 29789186 A JP29789186 A JP 29789186A JP H0584879 B2 JPH0584879 B2 JP H0584879B2
Authority
JP
Japan
Prior art keywords
fuel
gripper
down tube
reactor
hold
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
JP61297891A
Other languages
Japanese (ja)
Other versions
JPS63150692A (en
Inventor
Hisao Funato
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 JP61297891A priority Critical patent/JPS63150692A/en
Publication of JPS63150692A publication Critical patent/JPS63150692A/en
Publication of JPH0584879B2 publication Critical patent/JPH0584879B2/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

  • Load-Engaging Elements For Cranes (AREA)
  • Liquid Carbonaceous Fuels (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 この発明は、高速増殖炉等を対象に、原子炉容
器に据付けて炉心との間で燃料交換を行う原子炉
の燃料交換装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a nuclear reactor fuel exchange device for fast breeder reactors and the like, which is installed in a nuclear reactor vessel and performs fuel exchange with the reactor core.

〔従来の技術〕[Conventional technology]

まず第3図により頭記燃料交換装置の従来構成
を示す。図において1は炉心2を収容した原子炉
容器、3はその上面に装備した遮蔽プラグ、4は
固定プラグ3の中央に装着した回転プラグ、5が
回転プラグ4に搭載して据付けたオフセツトアー
ム式燃料交換装置である。ここで燃料交換装置5
は炉外側の頂部に駆動部51を備え、回転プラグ
3を貫通して炉内側に挿入した本体軸部52と、
該本体軸部52の側方にオフセツトアーム53を
介して取付けられたホールドダウンチユーブ54
と、ホールドダウンチユーブ54の内部燃料通路
に沿つて昇降操作されるグリツパ55等で構成さ
れている。
First, FIG. 3 shows the conventional configuration of the fuel exchange device mentioned above. In the figure, 1 is the reactor vessel housing the reactor core 2, 3 is the shielding plug installed on its top surface, 4 is the rotating plug attached to the center of the fixed plug 3, and 5 is the offset arm installed on the rotating plug 4. It is a type fuel exchange device. Here, fuel exchange device 5
is equipped with a drive part 51 at the top of the outside of the furnace, and a main shaft part 52 inserted into the inside of the furnace through the rotary plug 3;
A hold down tube 54 is attached to the side of the main body shaft portion 52 via an offset arm 53.
, a gripper 55, etc., which is operated to move up and down along the internal fuel passage of the hold-down tube 54.

かかる燃料交換装置5の動作に付いては周知で
あり、回転プラグ4の回転、および燃料交換装置
5の本体軸部52の回転との組合せによる位置決
め操作でホールドダウンチユーブ54を炉心2側
での指定ポジシヨンにアクセスし、この位置でグ
リツパ55を昇降操作して燃料の抜取り、装荷等
の燃料交換を行う。
The operation of such a fuel exchange device 5 is well known, and the hold down tube 54 is moved to the core 2 side by a positioning operation in combination with the rotation of the rotary plug 4 and the rotation of the main body shaft portion 52 of the fuel exchange device 5. A designated position is accessed and the gripper 55 is raised and lowered at this position to perform fuel exchange such as removing fuel and loading.

一方、炉心2より抜取つた使用済燃料の炉外搬
出、および新燃料の炉内搬入のために原子炉容器
内には燃料交換装置5とは別に炉心2の側方に炉
内中継装置6が設置されており、該炉内中継装置
6を経由して炉外側に配備の燃料移送設備である
燃料出入機7との間で燃料の搬入、搬出を行うよ
うに構成されている。なお遮蔽プラグ3には燃料
出入通路31、およびそのドアバルブ32が設け
てある。ここで炉心2から抜取つた使用済燃料は
燃料交換装置5の移動操作により矢印イの経路を
たどつて炉内中継装置6に受け渡しされ、ここか
ら燃料出入機7の吊り上げ操作により矢印ロの経
路をたどつて炉外に搬出される。一方、新燃料は
前記とは逆に燃料出入機7の吊り降ろし操作で炉
内中継装置6に一旦受け渡しされ、ここから燃料
交換装置5の操作により燃料を受取つて炉心2に
装荷される。
On the other hand, an in-core relay device 6 is installed on the side of the reactor core 2 in addition to the fuel exchange device 5 inside the reactor vessel in order to carry out the spent fuel extracted from the reactor core 2 and to carry new fuel into the reactor. It is configured to carry in and out fuel via the in-furnace relay device 6 to a fuel loading/unloading machine 7, which is a fuel transfer facility located outside the furnace. The shielding plug 3 is provided with a fuel inlet/outlet passage 31 and a door valve 32 thereof. Here, the spent fuel extracted from the reactor core 2 is delivered to the in-core relay device 6 by moving the fuel exchange device 5, following the path shown by arrow A, and from there, by lifting the fuel inlet/output device 7, along the path shown by arrow B. It is carried out of the furnace by following the path. On the other hand, contrary to the above, the new fuel is once delivered to the in-core relay device 6 by the lifting and lowering operation of the fuel inlet/outlet device 7, and from there, the fuel is received by the operation of the fuel exchange device 5 and loaded into the reactor core 2.

〔発明が解決しようとする問題点〕[Problem that the invention seeks to solve]

上記のように従来の燃料交換装置では、燃料の
抜取り、装荷操作は勿論のこと炉内での燃料搬送
過程でも、ホールドダウンチユーブに収容した燃
料は上方からグリツパに吊り下げ把持されてい
る。したがつてこのままでは燃料の搬入、搬出に
際し、仮に燃料交換装置5と燃料出入機7との間
で直接燃料の受け渡しを行おうとしても、燃料交
換装置側のグリツパと燃料出入機側のグリツパと
が同じ方向から互いに干渉し合つて燃料の受け渡
しを行うことができない。このために従来では先
述のように原子炉容器内に炉内中継装置6を設置
し、燃料の搬入、搬出の際には燃料を炉内中継装
置6の中継点で燃料交換装置のグリツパ、あるい
は燃料出入機のグリツパから一旦切り離した上で
燃料の受け渡しを行うようにしている。
As described above, in the conventional fuel exchange apparatus, the fuel contained in the hold-down tube is suspended and gripped by the gripper from above, not only during fuel extraction and loading operations, but also during the fuel transportation process within the reactor. Therefore, when carrying in and out of fuel, even if it is attempted to transfer fuel directly between the fuel exchange device 5 and the fuel intake/discharge machine 7, the gripper on the fuel exchange system side and the gripper on the fuel intake/discharge machine side will They interfere with each other from the same direction, making it impossible to transfer fuel. For this purpose, conventionally, the in-core relay device 6 is installed inside the reactor vessel as described above, and when carrying in and out fuel, the fuel is transferred to the relay point of the in-core relay device 6 by the gripper of the fuel exchange device or The fuel is transferred after being disconnected from the gripper of the fuel inlet/outlet machine.

しかしながら上記のように原子炉容器1の内部
で炉心2の側方に炉内中継装置6を配備すること
は、それだけ炉内構造が複雑化するのみならず、
原子炉容器1が径大となり、かつこれに伴つて原
子炉格納容器も大きくなつて原子炉設備の建設費
のコストアツプを招くようになる。
However, disposing the in-core relay device 6 on the side of the reactor core 2 inside the reactor vessel 1 as described above not only complicates the in-reactor structure but also
The reactor vessel 1 becomes larger in diameter, and the reactor containment vessel also becomes larger accordingly, leading to an increase in the construction cost of the nuclear reactor equipment.

この発明の目的は、炉内中継装置を経由するこ
となく燃料交換装置と炉外側の燃料移送設備との
間で直接燃料の受け渡しが行えるようにすること
により、炉内中継装置を省略して原子炉容器を含
む原子炉設備全体の小形、コンパクト化が図れる
ようにした原子炉の燃料交換装置を提供すること
にある。
The purpose of this invention is to enable direct transfer of fuel between the fuel exchange device and the fuel transfer equipment outside the reactor without going through the in-core relay device, thereby omitting the in-core relay device. It is an object of the present invention to provide a fuel exchange device for a nuclear reactor, which allows the entire nuclear reactor equipment including the reactor vessel to be made smaller and more compact.

〔問題点を解決するための手段〕[Means for solving problems]

上記問題点を解決するために、この発明によれ
ば、グリツパをホールドダウンチユーブの頂部側
方へ回避させる回転回避機構、およびホールドダ
ウンチユーブ内の燃料通路へ側方より出入操作さ
れる燃料支え用の下部支持台を備えて構成するも
のとする。
In order to solve the above problems, the present invention provides a rotation avoidance mechanism that avoids the gripper to the side of the top of the holddown tube, and a rotation avoidance mechanism that avoids the gripper toward the side of the top of the holddown tube, and a rotation avoidance mechanism that prevents the gripper from moving in and out of the fuel passage in the holddown tube from the side. It shall be constructed with a lower support stand.

〔作用〕[Effect]

上記の構成において、燃料交換時にはグリツパ
をホールドダウンチユーブのセンタに位置させ、
かつ前記下部支持台を燃料通路外に後退させた状
態でグリツパの昇降操作により炉心との間で燃料
装荷、抜取りの交換作業を行う。一方、燃料の搬
入、搬出の際には、グリツパをホールドダウンチ
ユーブの頂部側方へ回転回避させ、かつ下部支持
台を燃料通路内へ突出した状態でホールドダウン
チユーブを炉外の燃料移送設備との対応位置へ移
動させるることにより、グリツパとの干渉無しに
燃料移送設備とホールドダウンチユーブの間で直
接燃料の受け渡しを行うことができる。
In the above configuration, when replacing fuel, the gripper is located at the center of the hold-down tube,
With the lower support stand retracted out of the fuel passage, exchange operations such as loading and unloading fuel with the core are performed by raising and lowering the gripper. On the other hand, when carrying in and out fuel, the gripper is rotated to the side of the top of the hold-down tube and the lower support is protruded into the fuel passage, and the hold-down tube is connected to the fuel transfer equipment outside the reactor. By moving the hold-down tube to the corresponding position, fuel can be transferred directly between the fuel transfer equipment and the hold-down tube without interference with the gripper.

〔実施例〕〔Example〕

第1図、第2図はこの発明の実施例による燃料
交換装置の構造を示すものであり、第3図に対応
する同一部材には同じ符号が付してある。
1 and 2 show the structure of a fuel exchange device according to an embodiment of the present invention, and the same members corresponding to those in FIG. 3 are given the same reference numerals.

すなわちこの発明により、まず燃料交換装置5
のグリツパ55は、ホールドダウンチユーブ54
と平行してその側方位置でオフセツトアーム53
に支持された昇降ガイドレール8に対し、ここに
敷設されたボールねじ9へナツト10を介して結
合され、かつボールねじ9は下端側で歯車機構1
1、駆動軸12を介して燃料交換装置5の駆動部
51に伝動連結されている。さらに前記ガイドレ
ール8はグリツパ55を搭載支持したままその軸
の回りに自転可能なようにオフセツトアーム53
に軸受支持されており、かつガイドレール8はそ
の周面上に設けた歯車機構13、駆動軸14を介
して駆動部51に伝動連結されている。
That is, according to this invention, first, the fuel exchange device 5
The gripper 55 of the hold down tube 54
offset arm 53 in its lateral position parallel to
The lifting guide rail 8 supported by the lift guide rail 8 is connected via a nut 10 to a ball screw 9 installed here, and the ball screw 9 is connected to the gear mechanism 1 at the lower end side.
1. It is transmission-connected to the drive part 51 of the fuel exchange device 5 via the drive shaft 12. Further, the guide rail 8 has an offset arm 53 so as to be able to rotate around its axis while mounting and supporting the gripper 55.
The guide rail 8 is supported by a bearing, and the guide rail 8 is transmission-connected to a drive section 51 via a gear mechanism 13 and a drive shaft 14 provided on the circumferential surface of the guide rail 8.

かかる構成で駆動部51より駆動軸12をいず
れかの方向に回転操作することにより、グリツパ
55はボールねじ9にねじ送りされて矢印Aの方
向へ昇降操作される。また駆動軸14を回転操作
することにより、グリツパ55はガイドレール8
とともに矢印B方向に回転操作される。なおグリ
ツパ55はホールドダウンチユーブ54の上端よ
りもさらに上方位置まで上昇して引出し可能なよ
うにボールねじ9の長さが選定されている。
With this configuration, when the drive shaft 12 is rotated in any direction by the drive unit 51, the gripper 55 is threaded by the ball screw 9 and is moved up and down in the direction of arrow A. Also, by rotating the drive shaft 14, the gripper 55 is moved to the guide rail 8.
At the same time, the rotation operation is performed in the direction of arrow B. The length of the ball screw 9 is selected so that the gripper 55 can be raised to a position further above the upper end of the hold-down tube 54 and pulled out.

一方、ホールドダウンチユーブ54内の燃料通
路の下部途中箇所には符号56で示す開閉式の下
部支持台が配備されている。この下部支持台56
はその操作機構により燃料通路内へ向けて後方か
ら矢印C方向へ回動式に開閉して出入操作される
ものであり、その操作機構として下部支持台56
が後端に結合した歯車機構(図示せず)、および
駆動軸15を介して燃料交換装置の駆動部51に
伝動連結されている。
On the other hand, an openable and closable lower support stand indicated by reference numeral 56 is provided at a midway point in the lower part of the fuel passage in the hold-down tube 54 . This lower support stand 56
is operated by its operating mechanism to rotate in and out from the rear in the direction of arrow C toward the inside of the fuel passage, and the lower support base 56 serves as the operating mechanism.
is transmission-coupled to a drive unit 51 of the refueling device via a gear mechanism (not shown) coupled to the rear end and a drive shaft 15.

次に上記構成による炉外側燃料移送設備の燃料
出入機との間で行う燃料受け渡し動作、並びに炉
心との間で行う燃料交換動作に付いて述べる。炉
外より新燃料を搬入して炉心に装荷する場合に
は、まず回転プラグ4、および燃料交換装置の本
体軸部52を回転による位置決め操作でホールド
ダウンチユーブ54を固定プラグ3に開口した燃
料出入口31の直下位置に移動させる。続いて第
1図のようにグリツパ55を最上位置に上昇させ
てホールドダウンチユーブ54より抜き出し、さ
らに下部支持台56を図示のようにホールドダウ
ンチユーブ内の燃料通路内へ突出した上で、グリ
ツパのガイドレール8を回転操作してグリツパ5
5を第2図に示すようにホールドダウンチユーブ
54の頂部より側方へ回避移動させる。次にこの
状態で炉外側の燃料出入機7の操作により燃料1
6を固定プラグ3の燃料出入口31を通じて炉内
側へ吊り降ろし、その直下に待機しているホール
ドダウンチユーブ54の中に収容して下部支持台
56上に着地支持させた後に燃料出入機7のグリ
ツパと燃料16との間を切り離すとともに、続い
てガイドレール8を回転操作してグリツパ55を
ホールドダウンチユーブ54のセンタ位置に戻
す。
Next, a description will be given of the fuel transfer operation performed between the fuel transfer equipment outside the reactor having the above configuration and the fuel inlet/output machine, and the fuel exchange operation performed between the reactor core and the reactor core. When carrying in new fuel from outside the reactor and loading it into the reactor core, first position the rotary plug 4 and the main body shaft part 52 of the fuel exchange device by rotating the hold-down tube 54 to open the fuel inlet/outlet to the fixed plug 3. Move it to the position directly below 31. Next, as shown in FIG. 1, the gripper 55 is raised to the uppermost position and pulled out from the hold-down tube 54, and the lower support base 56 is further protruded into the fuel passage in the hold-down tube as shown in the figure, and then the gripper is removed. The gripper 5 is rotated by rotating the guide rail 8.
5 is moved sideways from the top of the hold-down tube 54 as shown in FIG. Next, in this state, the fuel 1 is
6 is suspended into the reactor through the fuel inlet/outlet 31 of the fixed plug 3, accommodated in the hold down tube 54 waiting just below, and landed and supported on the lower support base 56, after which the gripper of the fuel inlet/outlet machine 7 is and the fuel 16, and then rotate the guide rail 8 to return the gripper 55 to the center position of the hold-down tube 54.

これにより新燃料の炉内搬入受け渡し操作が終
了し、続いてグリツパ55を下降操作して燃料1
6と結合した後にグリツパとともに燃料16を一
旦上昇させた状態でいままで図示のように燃料通
路へ突出していた下部支持台56を縦姿勢に倒立
させるように燃料通路より後退操作する。次に回
転プラグ4の回転、および燃料交換装置5の本体
軸52の回転とによに位置決め操作でホールドダ
ウンチユーブ54を炉心側の指定ポジシヨンへア
クセスし、この位置でグリツパ55を下降操作し
て燃料16を炉心へ装荷させる。
This completes the transfer operation of new fuel into the reactor, and then lowers the gripper 55 to remove the fuel 1.
6, the fuel 16 is once raised together with the gripper, and the lower support 56, which has been protruding into the fuel passage as shown in the figure, is moved backward from the fuel passage so as to be inverted in a vertical position. Next, the hold-down tube 54 is accessed to a designated position on the core side by a positioning operation according to the rotation of the rotary plug 4 and the rotation of the main body shaft 52 of the fuel exchange device 5, and at this position, the gripper 55 is lowered. Fuel 16 is loaded into the core.

一方、炉心から使用済燃料を抜取つて炉外に搬
出する場合には、前記操作とは逆にまず下部支持
台56をホールドダウンチユーブ54の燃料通路
より後退させた状態で回転プラグおよび燃料交換
装置5の回転位置決め操作でホールドダウンチユ
ーブ54を炉心側の指定ポジシヨンへアクセス
し、ここでグリツパ55を操作して炉心より使用
済燃料を抜取り、ホールドダウンチユーブ内に回
収する。次にグリツパ55で把持したまま燃料1
6を一旦最上位置まで上昇させた状態で下部支持
台56を燃料通路内に突出し操作し、再びグリツ
パ55を下降操作して燃料16を下部支持台56
の上に着地させる。続いてグリツパ55を燃料1
6より切り離し、再度グリツパ55を上昇操作し
てホールドダウンチユーブ外に引出した上で第2
図のようにガイドレール8を回転操作してグリツ
パ55をホールドダウンチユーブ54の頂部側方
へ回転回避させる。
On the other hand, when the spent fuel is extracted from the core and carried out of the reactor, contrary to the above operation, the lower support 56 is first retracted from the fuel passage of the hold-down tube 54, and then the rotary plug and fuel exchanger The hold-down tube 54 is accessed to a designated position on the core side by the rotational positioning operation in step 5, and the gripper 55 is operated here to extract the spent fuel from the core and collect it in the hold-down tube. Next, while holding the fuel 1 with the grippers 55,
6 is raised to the highest position, the lower support stand 56 is operated to protrude into the fuel passage, and the gripper 55 is again lowered to move the fuel 16 to the lower support stand 56.
to land on top of. Next, use Gritzpa 55 as fuel 1
6, lift the gripper 55 again to pull it out of the hold-down tube, and then
As shown in the figure, the guide rail 8 is rotated to avoid rotation of the gripper 55 toward the top side of the hold-down tube 54.

次に燃料16を収容したまま燃料交換装置5を
を炉外受け渡し位置まで移動し、ここで炉外側の
燃料出入機7を操作してホールドダウンチユーブ
54内に収容されている使用済燃料を吊り上げて
炉外へ搬出する。なおホールドダウンチユーブ5
4と燃料出入機7との間で燃料の受け渡しを行う
際には、前述のようにグリツパ55はホールドダ
ウンチユーブ54の頂部側方に回転回避されてお
り、したがつてグリツパ55との干渉無しに燃料
交換装置5と燃料出入機7との間で燃料16を直
接受け渡しを行うことができる。
Next, the fuel exchange device 5 is moved to the delivery position outside the reactor while still containing the fuel 16, and here the fuel inlet/output machine 7 outside the reactor is operated to lift up the spent fuel accommodated in the hold-down tube 54. and remove it from the furnace. Furthermore, hold down tube 5
4 and the fuel inlet/outlet device 7, the gripper 55 is prevented from rotating to the side of the top of the hold-down tube 54 as described above, so there is no interference with the gripper 55. The fuel 16 can be directly transferred between the fuel exchange device 5 and the fuel intake/discharge machine 7.

〔発明の効果〕〔Effect of the invention〕

以上述べたようにこの発明によれば、グリツパ
をホールドダウンチユーブの頂部側方へ回避させ
る回転回避機構、およびホールドダウンチユーブ
内の燃料通路へ側方より出入操作される燃料支え
用の下部支持台を備え、グリツパをホールドダウ
ンチユーブのセンタに位置させ、かつ前記下部支
持台を燃料通路外に後退させた状態でグリツパの
昇降位置により炉心との間で燃料交換を行い、グ
リツパをホールドダウンチユーブの頂部側方へ回
転回避させ、かつ下部支持台を燃料通路内へ突出
した状態で炉外の燃料移送設備とホールドダウン
チユーブの間で直接燃料の受け渡しを行うよう構
成したことにより、従来装置で必要としていた炉
内中継装置を省略して炉外側の燃料搬送設備との
間で直接燃料の受け渡しを行うことができ、これ
により炉内構造の簡略化、並びに原子炉容器を含
めた原子炉設備の小形、コンパクト化が可能とな
る。
As described above, according to the present invention, there is provided a rotation avoidance mechanism that avoids the gripper toward the top side of the hold-down tube, and a lower support for supporting fuel that is operated from the side to enter and exit the fuel passage in the hold-down tube. With the gripper positioned at the center of the hold-down tube and the lower support stand retracted outside the fuel passage, fuel exchange is performed between the core and the gripper by the vertical position of the gripper, and the gripper is positioned at the center of the hold-down tube. By avoiding rotation of the top to the side and directly transferring fuel between the fuel transfer equipment outside the reactor and the hold-down tube with the lower support protruding into the fuel passage, this design eliminates the need for conventional equipment. It is possible to omit the in-core relay device that was previously used and to directly transfer fuel to the fuel transfer equipment outside the reactor, which simplifies the reactor internal structure and improves the efficiency of reactor equipment including the reactor vessel. It is possible to make it smaller and more compact.

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

第1図は本発明実施例による燃料交換装置全体
の構成断面図、第2図は第1図における要部構造
の横断面図、第3図は従来における燃料交換装置
の構成図である。各図において、 1……原子炉容器、2……炉心、4……回転プ
ラグ、5……燃料交換装置、7……炉外燃料移送
設備の燃料出入機、8……グリツパのガイドレー
ル、9……グリツパ昇降操作用のボールねじ、1
3……グリツパ回転回避機構の歯車機構、14…
…グリツパ回転回避機構の駆動軸、51……燃料
交換装置の駆動部、52……本体軸部、53……
オフセツトアーム、54……ホールドダウンチユ
ーブ、55……グリツパ、56……下部支持台。
FIG. 1 is a cross-sectional view of the entire structure of a fuel exchange device according to an embodiment of the present invention, FIG. 2 is a cross-sectional view of the main structure of FIG. 1, and FIG. 3 is a block diagram of a conventional fuel exchange device. In each figure, 1...Reactor vessel, 2...Reactor core, 4...Rotating plug, 5...Fuel exchange device, 7...Fuel inlet/output machine of extra-core fuel transfer equipment, 8...Gripper guide rail, 9...Ball screw for gripper lifting/lowering operation, 1
3...Gear mechanism of gripper rotation avoidance mechanism, 14...
... Drive shaft of gripper rotation avoidance mechanism, 51 ... Drive section of fuel exchange device, 52 ... Main body shaft section, 53 ...
Offset arm, 54... hold down tube, 55... gripper, 56... lower support base.

Claims (1)

【特許請求の範囲】 1 原子炉容器の上部回転プラグに据付けて炉心
との間で燃料交換を行う原子炉の燃料交換装置で
あり、頂部に駆動部を装備して回転プラグに搭載
支持された本体軸部と、該本体軸部の側方にオフ
セツトアームを介して支持されたホールドダウン
チユーブと、該ホールドダウンチユーブに沿つて
昇降操作されるグリツパを備えて成るものにおい
て、前記グリツパをホールドダウンチユーブの頂
部側方へ回避させる回転回避機構、およびホール
ドダウンチユーブ内の燃料通路へ側方より出入操
作される燃料支え用の下部支持台を備え、グリツ
パをホールドダウンチユーブのセンタに位置さ
せ、かつ前記下部支持台を燃料通路外に後退させ
た状態でグリツパの昇降操作により炉心との間で
燃料交換を行い、グリツパをホールドダウンチユ
ーブの頂部側方へ回転回避させ、かつ下部支持台
を燃料通路内へ突出した状態で炉外の燃料移送設
備とホールドダウンチユーブの間で直接燃料の受
け渡しを行うよう構成したことを特徴とする原子
炉の燃料交換装置。 2 特許請求の範囲第1項記載の燃料交換装置に
おいて、グリツパの回転回避機構として、燃料交
換装置のオフセツトアームに自転可能に支持され
たグリツパのガイドレールが歯車機構、駆動軸を
介して駆動部に伝動連結されていることを特徴と
する原子炉の燃料交換装置。
[Claims] 1. A nuclear reactor fuel exchange device installed on the upper rotating plug of a reactor vessel to exchange fuel with the reactor core, which is equipped with a drive section at the top and is mounted and supported on the rotating plug. A gripper comprising: a main body shaft; a hold down tube supported on the side of the main body shaft via an offset arm; and a gripper that is operated up and down along the hold down tube. A rotation avoidance mechanism that avoids the top of the down tube to the side, and a lower support for supporting fuel that is operated from the side into and out of the fuel passage in the hold down tube, and the gripper is located at the center of the hold down tube, Then, with the lower support stand retracted outside the fuel passage, fuel is exchanged with the reactor core by raising and lowering the gripper, the gripper is prevented from rotating to the side of the top of the hold-down tube, and the lower support stand is removed from the fuel passage. A fuel exchange device for a nuclear reactor, characterized in that it is configured to directly transfer fuel between a fuel transfer facility outside the reactor and a holddown tube in a state that projects into a passage. 2. In the fuel exchange device according to claim 1, the guide rail of the gripper, which is rotatably supported by the offset arm of the fuel exchange device, is driven via a gear mechanism and a drive shaft, as the gripper rotation avoidance mechanism. A fuel exchange device for a nuclear reactor, characterized in that the device is transmission-coupled to the section.
JP61297891A 1986-12-15 1986-12-15 Fuel exchanger for nuclear reactor Granted JPS63150692A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61297891A JPS63150692A (en) 1986-12-15 1986-12-15 Fuel exchanger for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61297891A JPS63150692A (en) 1986-12-15 1986-12-15 Fuel exchanger for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS63150692A JPS63150692A (en) 1988-06-23
JPH0584879B2 true JPH0584879B2 (en) 1993-12-03

Family

ID=17852446

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61297891A Granted JPS63150692A (en) 1986-12-15 1986-12-15 Fuel exchanger for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS63150692A (en)

Also Published As

Publication number Publication date
JPS63150692A (en) 1988-06-23

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