JPS63150692A - Fuel exchanger for nuclear reactor - Google Patents

Fuel exchanger for nuclear reactor

Info

Publication number
JPS63150692A
JPS63150692A JP61297891A JP29789186A JPS63150692A JP S63150692 A JPS63150692 A JP S63150692A JP 61297891 A JP61297891 A JP 61297891A JP 29789186 A JP29789186 A JP 29789186A JP S63150692 A JPS63150692 A JP S63150692A
Authority
JP
Japan
Prior art keywords
fuel
gripper
down tube
hold
reactor
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
JP61297891A
Other languages
Japanese (ja)
Other versions
JPH0584879B2 (en
Inventor
船戸 久雄
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

  • Liquid Carbonaceous Fuels (AREA)
  • Load-Engaging Elements For Cranes (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〕 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0
図においてl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
けたオフセノトア−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41を備え3回転
プラグ3を貫通して炉内側に挿入した本体軸部42と、
該本体軸部42の側方にオフセットアーム43を介して
取付けられたホールドダウンチューブ44と、ホールド
ダウンチューブ44の内部燃料通路に沿って昇降操作さ
れるグリッパ45等で構成されている。
First, FIG. 3 shows the conventional configuration of the above-mentioned fuel exchange device.
In the figure, l is the reactor vessel that houses 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 off-cenotor arm installed on the rotating plug 4. It is a type fuel exchange device. Here, the fuel exchange device 5 has a drive part 41 at the top of the outside of the furnace, and a main shaft part 42 that penetrates the three-turn plug 3 and is inserted into the inside of the furnace.
It is comprised of a hold down tube 44 attached to the side of the main body shaft portion 42 via an offset arm 43, a gripper 45 that is moved up and down along the internal fuel passage of the hold down tube 44, and the like.

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5
2の回転との組合せによる位置決め操作でホールドダウ
ンチューブ54を炉心2側での指定ポジションにアクセ
スし、この位置でグリッパ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 includes the rotation of the rotary plug 4 and the main body shaft portion 5 of the fuel exchange device 5.
The hold-down tube 54 is accessed to a designated position on the core 2 side by the positioning operation in combination with the rotation of 2, and at this position, the gripper 55 is raised and lowered to perform fuel exchange such as fuel removal and loading.

一方、炉心2より抜取った使用済燃料の炉外搬出3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W6が設!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、
逆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
である。ここで炉心2から抜取っ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って炉内
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口の経路をたどって炉外に搬出さ
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4の操作により燃料を受取って炉心2
に装荷される。
On the other hand, in addition to the fuel exchange device 5, an in-core relay device W6 is installed on the side of the reactor core 2 in the reactor vessel for carrying out the spent fuel extracted from the reactor core 2 and carrying new fuel into the reactor. Established! The fuel is transferred via the in-core relay device 6 to the fuel inlet/output machine 7, which is a fuel transfer equipment installed outside the reactor.
It is configured to perform reverse output. The shielding plug 3 has a fuel inlet/outlet passage 31. And its door valve 32 is provided. Here, the spent fuel extracted from the reactor core 2 is transferred 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, it is transferred to the in-core relay device 6, following the path shown by arrow A. is carried out of the furnace. On the other hand, contrary to the above, 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, fuel is received by the operation of the fuel exchange device 4 and transferred to the reactor core.
is loaded.

〔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
ルドダウンチューブに収容した燃料は上方からグリッパ
に吊り下げ把持されている。
As mentioned above, conventional fuel exchange equipment requires the removal of fuel,
During the loading operation as well as the fuel transport process within the reactor, the fuel contained in the hold-down tube is suspended and gripped by the gripper from above.

したがっ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ッパと燃
料出入機側のグリッパとが同じ方向から互いに干渉し合
っ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ッパ、あるいは燃料出
入機のグリッ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。
Therefore, if the fuel exchange device 5 and the fuel inlet/outlet machine 7 try to directly transfer fuel when carrying in and out fuel, the gripper on the fuel exchange device side and the gripper on the fuel inlet/outlet machine side will be the same. They interfere with each other from both directions, making it impossible to transfer fuel. For this purpose, in the past, the in-core relay device 6 was installed inside the reactor vessel as described above, and when carrying in and out the fuel, the fuel was transferred to the gripper of the fuel exchange device or at the relay point of the in-core relay device 6. The fuel is transferred after being separated from the gripper of the fuel loading/unloading 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W6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。
However, as mentioned above, inside the reactor vessel 1, the reactor core 2
Placing the in-core relay equipment W6 on the side of the reactor not only complicates the in-core structure accordingly.

原子炉容器1が径大となり、かつこれに伴って原子炉格
納容器も太き(なって原子炉設備の建設費のコストアン
プを招くようになる。
The diameter of the reactor vessel 1 becomes larger, and the reactor containment vessel also becomes thicker (this results in an increase in the construction cost of the 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.

c問題点を解決するための手段〕 上記問題点を解決するために、この発明によれば、グリ
ッパをホールドダウンチュ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ューブ内の燃料
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
を備えて燐酸するものとする。
Means for Solving Problem c] In order to solve the above problem, according to the present invention, a rotation avoidance mechanism that avoids the gripper to the top side of the holddown tube, and 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 to the side of the top of the holddown tube, It shall be equipped with a lower support for supporting fuel that can be accessed and removed from the side.

〔作用〕[Effect]

上記の構成において、燃料交換時にはグリッパをホール
ドダウンチューブのセンタに位置させ。
In the above configuration, the gripper is positioned at the center of the hold-down tube during fuel exchange.

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
リッ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、
グリッパをホールドダウンチュ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
ホールドダウンチュ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、グリッパとの干渉無し
に燃料移送設備とホールドダウンチューブの間で直接燃
料の受け渡しを行うことができる。
With the lower support stand retracted out of the fuel passage, the gripper is moved up and down to carry out fuel loading and unloading operations with respect to the reactor core. On the other hand, when transporting fuel,
By avoiding rotation of the gripper to the side of the top of the hold-down tube and moving the hold-down tube to a position corresponding to the fuel transfer equipment outside the reactor with the lower support protruding into the fuel passage, the gripper and Fuel can be transferred directly between the fuel transfer equipment and the holddown tube without interference.

〔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
は同し符号が付しである。
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のグリッ
パ55は、ホールドダウンチューブ54と平行してその
側方位置でオフセットアーム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し9ヘナ
ノト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11.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はグリッパ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ットアーム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 the present invention, first, the gripper 55 of the fuel exchange device 5 is attached to a ball cage installed on the lifting guide rail 8 which is parallel to the hold down tube 54 and supported by the offset arm 53 at a lateral position thereof. 9 are connected via a hexagonal nut 10, and the ball screw 9 is connected to a gear mechanism 11. It is transmission connected to a drive section 51 of the fuel exchange device 5 via a drive shaft 12 . Further, the guide rail 8 is supported by a bearing on an offset arm 53 so as to be able to rotate about its axis while supporting the gripper 55, and the guide rail 8 is supported by a gear mechanism 13 provided on its circumferential surface. It is transmission-coupled to the drive section 51 via the drive shaft 14 .

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、グリッパ55はボールね
し9にねじ送りされて矢印Aの方向へ昇降操作される。
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.

また駆動軸14を回転操作することにより、グリッパ5
5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。なおグリッパ55はホールドダウンチューブ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
うにボールねし9の長さが選定されている。
Also, by rotating the drive shaft 14, the gripper 5
5 is rotated in the direction of arrow B together with the guide rail 8. 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、ホールドダウンチューブ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)1
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 the 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 of the fuel passage from the rear in the direction of arrow C, and the lower support stand 56 is connected to the rear end as the operating mechanism. gear mechanism (not shown) 1
and is transmission-coupled via a drive shaft 15 to a drive section 51 of the fuel exchange device.

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
の間で行う燃料費は渡し動作、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ューブ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
図のようにグリッパ55を最上位置に上昇させてホール
ドダウンチューブ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ューブ内の燃料通
路内へ突出した上で、グリッパのガイドレール8を回転
操作してグリッパ55を第2図に示すようにホールドダ
ウンチューブ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ュ
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のグリッパと燃料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
グリッパ55をホールドダウンチューブ54のセンタ位
置に戻す。
Next, the fuel costs for the transfer operation between the fuel transfer equipment outside the reactor and the fuel inlet/output machine of the above-mentioned configuration will be described with respect to the transfer operation and the fuel exchange operation performed between the reactor core and the reactor core. When bringing in new fuel from outside the reactor and loading it into the reactor core, first move the rotary plug 4. Then, the hold-down tube 54 is moved to a position directly below the fuel inlet/outlet 31 opened in the fixed plug 3 by a positioning operation by rotating the main body shaft portion 52 of the fuel exchange device. Then the first
As shown in the figure, raise the gripper 55 to the highest position and pull it out from the hold-down tube 54. Further, as shown in the figure, after protruding the lower support base 56 into the fuel passage in the hold-down tube, remove the guide rail 8 of the gripper. Rotation is performed to move the gripper 55 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 inside of the reactor through the fuel inlet/outlet 31 of the fixed plug 3, accommodated in the hold down tube 54 waiting just below it, and landed and supported on the lower support stand 56, after which the gripper of the fuel inlet/outlet machine 7 is suspended. 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費は渡し操作が終了し、続
いてグリッパ55を下降操作して燃料16と結合した後
にグリッパとともに燃料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0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
ウンチューブ54を炉心側の指定ポジションへアクセス
し、この位置でグリッパ55を下降操作して燃料16を
炉心へ装荷させる。
As a result, the cost of transporting new fuel into the reactor is reduced by completing the transfer operation, and then lowering the gripper 55 to combine it with the fuel 16.Then, the fuel 16 is once raised together with the gripper, and the fuel passage is as shown in the figure. The rotation of the rotary plug 4 and the fuel exchange device 5 are performed by retracting the lower support base 56 from the fuel passage so as to invert the lower support base 56 that had been protruding into the vertical position.
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 main body shaft 52, and at this position, the gripper 55 is lowered to load the fuel 16 into the core.

一方、炉心から使用済燃料を抜取っ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
ドダウンチューブ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tfA装置5の回転位置決め操
作でホールドダウンチューブ54を炉心側の指定ポジシ
ョンへアクセスし、ここでグリッパ55を操作して炉心
より使用済燃料を抜取り、ホールドダウンチューブ内に
回収する0次にグリッパ55で把持したまま燃料16を
一旦最上位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、再びグリッパ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
グリッパ55を燃料16より切り離し、再度グリッパ5
5を上昇操作してホールドダウンチューブ外に引出した
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
ッパ55をホールドダウンチューブ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 are removed. The hold-down tube 54 is accessed to a designated position on the core side by the rotational positioning operation of the tfA device 5, and the gripper 55 is operated here to extract the spent fuel from the core and collect it in the hold-down tube. The lower support 56 is operated to project into the fuel passage after the fuel 16 is raised to the highest level while being gripped by the lower support 56, and the gripper 55 is lowered again to cause the fuel 16 to land on the lower support 56. Subsequently, the gripper 55 is separated from the fuel 16, and the gripper 55 is removed again.
5 to the outside of the hold-down tube, and then rotate the guide rail 8 as shown in FIG. 2 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ューブ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
ドダウンチューブ54と燃料出入機7との間で燃料の受
け渡しを行う際には、前述のようにグリッパ55はホー
ルドダウンチューブ54の頂部側方に回転回避されてお
り、したがってグリッパ55との干渉無しに燃料交換袋
W5と燃料出入[7との間で燃料16を直接光は渡しを
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. Note that when transferring fuel between the hold down tube 54 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 that the rotation between the gripper 55 and the gripper 55 is avoided. The fuel 16 can be directly transferred between the fuel exchange bag W5 and the fuel inlet/outlet [7] without interference.

〔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、グリッパをホール
ドダウンチュ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ュ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
ッパをホールドダウンチュ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
ッパの昇降操作により炉心との間で燃料交換を行い、グ
リッパをホールドダウンチュ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ューブの間で直接
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 to the side of the top of the hold-down tube, and a lower support for supporting fuel that is operated in and out of the fuel passage in the hold-down tube from the side. With the gripper positioned at the center of the hold-down tube and the lower support stand retracted out of the fuel passage, fuel exchange is performed between the core and the reactor core by raising and lowering 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ニゲ
リツパのガイドレール、9ニゲリッパ昇降操作用のボー
ルねし、13;グリッパ回転回避機構の歯車機構、14
ニゲリッ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:オフセットアーム、
54:ホールドダウンチューブ、55;グリッパ、56
:下部支持台。 互燃料灯夾Xi 第1図
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: Core, 4: Rotating plug, 5: Fuel exchange device, 7: Fuel inlet/output machine for extra-core fuel transfer equipment, 8 Guide rail for Nigelipper, 9 Ball for lifting and lowering the Nigelipper. Gear mechanism of gripper rotation avoidance mechanism, 14
Drive shaft of nigeripper rotation avoidance mechanism, 51; Drive part of fuel exchange device, 52; Main body shaft part, 53: Offset arm,
54: Hold down tube, 55; Gripper, 56
: Lower support base. Mutual Fuel Lantern Xi Figure 1

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ットアームを介して支持
されたホールドダウンチューブと、該ホールドダウンチ
ューブに沿って昇降操作されるグリッパを備えて成るも
のにおいて、前記グリッパをホールドダウンチューブの
頂部側方へ回避させる回転回避機構、およびホールドダ
ウンチュ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、グリッパをホールドダウ
ンチュ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ッパの昇降操作によ
り炉心との間で燃料交換を行い、グリッパをホールドダ
ウンチュ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
ホールドダウンチュ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
、グリッパの回転回避機構として、燃料交換装置のオフ
セットアームに自転可能に支持されたグリッパのガイド
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。
[Scope of Claims] 1) A nuclear reactor fuel exchange device that is installed on the upper rotating plug of a reactor vessel and performs fuel exchange with the reactor core, and is equipped with a drive section at the top and is mounted and supported on the rotating plug. a main body shaft, a hold-down tube supported on the side of the main body shaft through an offset arm, and a gripper that is operated up and down along the hold-down tube, wherein the gripper is held. It includes 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 in and out of the fuel passage in the hold down tube from the side, and positions the gripper 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. 1. A fuel exchange device for a nuclear reactor, characterized in that the fuel exchange device for a nuclear reactor is configured to directly transfer fuel between a fuel transfer facility outside the reactor and a hold-down tube in a state protruding 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 true JPS63150692A (en) 1988-06-23
JPH0584879B2 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
JPH0584879B2 (en) 1993-12-03

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