JPH0679072B2 - Refueling device for nuclear reactor - Google Patents

Refueling device for nuclear reactor

Info

Publication number
JPH0679072B2
JPH0679072B2 JP61265561A JP26556186A JPH0679072B2 JP H0679072 B2 JPH0679072 B2 JP H0679072B2 JP 61265561 A JP61265561 A JP 61265561A JP 26556186 A JP26556186 A JP 26556186A JP H0679072 B2 JPH0679072 B2 JP H0679072B2
Authority
JP
Japan
Prior art keywords
pulleys
gripper
pulley
reactor vessel
tube
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
JP61265561A
Other languages
Japanese (ja)
Other versions
JPS63120295A (en
Inventor
満 亀井
一 片岡
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.)
Doryokuro Kakunenryo Kaihatsu Jigyodan
Original Assignee
Doryokuro Kakunenryo Kaihatsu Jigyodan
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 Doryokuro Kakunenryo Kaihatsu Jigyodan filed Critical Doryokuro Kakunenryo Kaihatsu Jigyodan
Priority to JP61265561A priority Critical patent/JPH0679072B2/en
Publication of JPS63120295A publication Critical patent/JPS63120295A/en
Publication of JPH0679072B2 publication Critical patent/JPH0679072B2/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)
  • Liquid Carbonaceous Fuels (AREA)

Description

【発明の詳細な説明】 <産業上の利用分野> この発明は原子炉の燃料交換装置、特に、不透明で化学
的に活性な液体金属ナトリウムを冷却材として使用する
高速増殖炉の場合に好適な燃料交換装置に関するもので
ある。
DETAILED DESCRIPTION OF THE INVENTION <Industrial Field of Application> The present invention is suitable for a refueling apparatus for a nuclear reactor, particularly for a fast breeder reactor using opaque and chemically active liquid sodium metal as a coolant. The present invention relates to a fuel exchange device.

<従来の技術> 目視操作が不可能で、しかも原子炉容器の蓋を取外して
大気中に開けることが許されないナトリウム冷却高速炉
における燃料交換装置は、大別すると、遮蔽プラグ下操
作方式とホットセル方式とがあり、前者の遮蔽プラグ下
操作方式は、更に、単回転プラグ式,二重回転プラグ式
等に分類される。単回転プラグ式は、炉心からの放射線
と熱とを遮蔽する遮蔽プラグが、大円の固定プラグと、
偏心した位置に回転中心をもつ小円の回転プラグから成
り、回転プラグには制御棒駆動機構,燃料交換機など
が、固定プラグには炉内中継装置,回転プラグ駆動装置
などが搭載される。回転プラグと燃料交換機のホールド
ダウンアームを回転させることで、燃料交換機は炉心上
方のどの位置にも移動でき、このとき炉心上部機構は燃
料交換に支障を与えない側方の場所に移動することにな
る。二重回転プラグ方式では、大円と偏心した小円の両
遮蔽プラグ共、回転できるようになっていて、前記と同
様な働きを奏せしめる。これに対して、後者のホットセ
ル方式では、炉の上部をホットセルとして覆い、この中
で原子炉容器の蓋を開閉可能となし、ナトリウム液面を
下げて燃料集合体の頂部までを露出させ、テレビなどで
目視操作ができるようになっている。
<Prior Art> Fuel exchange devices in sodium-cooled fast reactors, which cannot be visually operated and are not allowed to be opened to the atmosphere by removing the lid of the reactor vessel, are roughly classified into the operation method under the shielded plug and the hot cell. The former operation method under the shielded plug is further classified into a single rotation plug type, a double rotation plug type and the like. In the single-rotation plug type, the shielding plug that shields the radiation and heat from the core is a large circular fixed plug,
It consists of a small circular rotary plug with its center of rotation in an eccentric position. The rotary plug is equipped with a control rod drive mechanism, a fuel exchanger, etc., and the fixed plug is equipped with an in-core relay device, a rotary plug drive device, etc. By rotating the rotating plug and the holddown arm of the refueling machine, the refueling machine can be moved to any position above the core, and at this time, the upper core mechanism is moved to a side position that does not hinder refueling. Become. In the double rotation plug system, both the large circle and the small eccentric circle shield plug can rotate, and the same function as described above can be achieved. On the other hand, in the latter hot cell system, the upper part of the reactor is covered as a hot cell, the lid of the reactor vessel can be opened and closed, and the sodium liquid level is lowered to expose the top of the fuel assembly, It is possible to perform visual operation by using such as.

<発明が解決しようとする問題点> 上記燃料交換機等を設置する回転プラグは、原子炉容器
の蓋を兼ね且つ熱や放射線を遮蔽するものではなければ
ならなかったから、その重量は100万KWeクラスで約3千
〜5千トンといった大重量物となり、製作するにしろ輸
送するにしろ大変であるほか、回転部のシールやベアリ
ング等々で建設費が高くつくし、保守も苦労するといっ
た点で問題は多かった。一方、ホットセル方式は、回転
プラグの場合に見られた問題はないが、大きな遮蔽用の
コンクリート製高温気密室を必要とし、そのホットセル
内には危険な放射性カバーガスが充満することになり、
また、ナトリウム蒸気の凝縮沈着も注意を要するといっ
た具合で、これまた問題があった。
<Problems to be Solved by the Invention> Since the rotating plug for installing the above-mentioned refueling machine and the like had to serve also as a lid of the reactor vessel and shield heat and radiation, its weight is 1 million KWe class. It becomes a heavy object of about 3,000 to 5,000 tons, and it is difficult to manufacture or transport, and the construction cost is high due to the seals and bearings of the rotating part, and maintenance is also difficult. There were many. On the other hand, the hot cell method does not have the problem found in the case of the rotating plug, but it requires a concrete high-temperature airtight chamber for large shielding, and the hot cell will be filled with dangerous radioactive cover gas.
In addition, the condensation and deposition of sodium vapor also requires attention, which is another problem.

この発明は、叙上のような実情に鑑み、原子炉容器の蓋
は回転プラグ構造とはせずに単なる固定の蓋となし、し
かもその蓋を開けずに燃料交換を行なう装置を提供する
ことを、その目的とするものである。
SUMMARY OF THE INVENTION In view of the above circumstances, the present invention provides a device for performing fuel exchange without opening the lid, without using the rotary plug structure for the lid of the reactor vessel and merely as a fixed lid. Is the purpose.

<問題点を解決するための手段> この発明は、原子炉容器の上部内周面に設けた無端レー
ルに2個の滑車を滑動自在に係合し、無端レール上での
各滑車の移動は炉外から操作可能とすること、これら2
個の滑車間で錘付きグリッパを内側に有するホールドダ
ウンチューブを懸垂保持し、該2個の滑車間でのホール
ドダウンチューブの移動は、前記滑車の場合と同様、炉
外から操作可能とすること、錘付きグリッパの昇降も、
また、炉外操作可能とすることによって、炉心上部機構
を上部のキャスク内に持ち上げたのち、2個の滑車位置
と、その間にあるホールドダウンチューブ位置とを適宜
移動させて、グリッパ位置を原子炉容器内の燃料一時貯
蔵ポット上方或いは炉心上方のどの位置にも設定でき、
したがって燃料交換を可能とするほか、2個の滑車を近
接させて、ホールドダウンチューブを炉心上部機構が所
定の位置に戻っても邪魔にはならない側方の場所に待機
させておくことができるようにしたものである。
<Means for Solving Problems> The present invention is such that two pulleys are slidably engaged with an endless rail provided on an upper inner peripheral surface of a reactor vessel, and each pulley is moved on the endless rail. Operable from outside the furnace, these 2
A holddown tube having a gripper with a weight inside is suspended between the pulleys, and the movement of the holddown tube between the two pulleys can be operated from the outside of the furnace as in the case of the pulleys. , Lifting the gripper with weight,
Further, by enabling the operation outside the reactor, the upper core mechanism is lifted into the upper cask, and then the two pulley positions and the holddown tube position between them are appropriately moved to move the gripper position to the reactor. It can be set at any position above the temporary fuel storage pot in the container or above the core,
Therefore, in addition to enabling refueling, it is possible to bring the two pulleys close to each other and hold the holddown tube in a side position where it will not interfere even if the core upper part mechanism returns to a predetermined position. It is the one.

<実施例> この発明を図面に示す実施例によって説明すると、つぎ
のとおりである。
<Example> The following will describe the present invention with reference to an example shown in the drawings.

第1図において、1は原子炉容器、2は原子炉容器1の
上部内周面に設けた無端レール、3,3は無端レール2に
滑動自在に係合した2個の滑車、4は2個の滑車3,3間
に懸垂保持したホールドダウンチューブ、5はホールド
ダウンチューブ4の内側に設けた錘付きグリッパであ
る。無端レール2を包持するようにして横転脱落のおそ
れをなくしている各滑車3,3の移動装置から説明する
と、各滑車3,3の両端にはそれぞれチェーン11,11を止着
していて(第2−C図参照)、それらのチェーン11,11
は、無端レール2およびこれと同心状に形成した無端ガ
イド12との間に環状通路を通り(第2−A図参照)、無
端レール2の大円をほぼ二等分する左右の箇所に各3個
宛配設したガイドプーリー13のうちの各2個宛使って、
右側で2本のチェーン11,11、左側で2本のチェーン11,
11をそれぞれ立ち上げる。一方、原子炉容器1の頂部を
密封する固定蓋7には前記立ち上がり箇所相当の部分に
貫通孔14,14を穿設すると共に、貫通孔14,14の外側には
気密保持用の密閉カバー8,8で覆ったチェーン巻取装置
6,6が装着されている。前記した左右で2本宛立ち上が
るチェーン11,11は固定蓋7の貫通孔14,14を通したの
と、それぞれチェーン巻取装置6,6と連結する(第1図
参照)。こうして適宜のチェーン巻取装置6,6を正回転
或いは逆回転することによって滑車3は時計方向或いは
反時計方向に滑動し、所望する設定位置に移動させるこ
とができる。
In FIG. 1, 1 is a reactor vessel, 2 is an endless rail provided on the upper inner peripheral surface of the reactor vessel 1, 3 and 3 are two pulleys slidably engaged with the endless rail 2, and 4 is 2 A holddown tube 5 suspended and held between the individual pulleys 3 and 3 is a gripper with a weight provided inside the holddown tube 4. Explaining from the moving device of each pulley 3 and 3 which encloses the endless rail 2 and eliminates the risk of falling over, the chains 11 and 11 are fastened to both ends of each pulley 3 and 3, respectively. (See Figure 2-C), their chains 11,11
Passes through an annular passage between the endless rail 2 and the endless guide 12 formed concentrically with the endless rail 2 (see FIG. 2-A), and the left and right portions of the great circle of the endless rail 2 are roughly divided into two parts. Using 2 of each of the 3 guide pulleys 13
Two chains 11,11 on the right side, two chains 11,11 on the left side
Launch 11 respectively. On the other hand, the fixed lid 7 for sealing the top of the reactor vessel 1 is provided with through holes 14 and 14 at the portion corresponding to the rising portion, and the outside of the through holes 14 and 14 is provided with a hermetic cover 8 for keeping airtightness. Chain winder covered with 8
6 and 6 are installed. The two chains 11, 11 that stand up to the left and right as described above are passed through the through holes 14, 14 of the fixed lid 7 and are connected to the chain winding devices 6, 6 respectively (see FIG. 1). In this way, the pulley 3 can be slid clockwise or counterclockwise by rotating the proper chain winding device 6, 6 in the forward or reverse direction, and can be moved to a desired set position.

つぎにホールドダウンチューブ4の移動装置を説明す
る。ホールドダウンチューブ4の上端には2本のチェー
ン15,15を止着していて(第2−B図参照)、それらの
チェーン15,15は、各滑車3,3に取付けた懸垂保持用や方
向変換用のガイドプーリー16,16を経て、無端ガイド12
と原子炉容器1内周面との間の環状通路を通し(第2−
A図参照)、前記した左右3個宛配設したガイドプーリ
ー13,13のうち残っているガイドプーリー13,13を使って
立ち上げ、固定蓋7の貫通孔14,14を通したのち、密閉
カバー8,8内のチェーン巻取装置6a,6aと連結する(第1
図参照)。こうして両チェーン巻取装置6a,6aを正回転
或いは逆回転することによって、2個の滑車3,3間で懸
垂保持されているホールドダウンチューブ4を所望する
設定位置に移動させることができる。
Next, a device for moving the holddown tube 4 will be described. Two chains 15 and 15 are fixed to the upper end of the hold-down tube 4 (see Fig. 2-B). These chains 15 and 15 are used for holding suspensions attached to the pulleys 3 and 3, respectively. Endless guide 12 through the guide pulleys 16, 16 for direction change
Through the annular passage between the inner peripheral surface of the reactor vessel 1 and
(See Fig. A), start up using the remaining guide pulleys 13, 13 among the above-mentioned guide pulleys 13, 13 arranged to the left and right, pass through the through holes 14, 14 of the fixed lid 7, and then seal. It is connected to the chain winding device 6a, 6a in the covers 8, 8 (first
See figure). In this way, the hold-down tube 4 suspended and held between the two pulleys 3 and 3 can be moved to a desired set position by rotating the chain winding devices 6a and 6a in the forward or reverse direction.

ホールドダウンチューブ4内の錘付きグリッパ5を昇降
させる装置は、つぎのようになっている。錘付きグリッ
パ5の頂部に止着した2本のチェーン17,17(第2−B
図参照)を、原子炉容器1内周面近くに設けたガイドロ
ーラ18,18で立ち上げて、固定蓋7に穿設した貫通孔19
を通し、その貫通孔19の外側に設けた密閉カバー8で覆
われたチェーン巻取装置6bと連結する(第1図参照)。
The device for raising and lowering the weighted gripper 5 in the holddown tube 4 is as follows. Two chains 17,17 (No. 2-B) fixed to the top of the gripper 5 with weight.
(See the figure) is started by guide rollers 18, 18 provided near the inner peripheral surface of the reactor vessel 1, and a through hole 19 is formed in the fixed lid 7.
Through the through hole 19 and is connected to the chain winding device 6b covered with the sealing cover 8 provided outside the through hole 19 (see FIG. 1).

固定蓋7にはキャスク9を形成し、このキャスク9内
に、制御棒駆動機構を含む炉心上部機構10を持ち上げ可
能とする(第1図参照)。これは炉心上部機構10が正規
の位置にあると燃料交換の際邪魔するから、邪魔しない
ところまで持ち上げておき、燃料交換作業が終了後、再
び炉心上部機構10を正規の位置に戻すようにする。
A cask 9 is formed on the fixed lid 7, and a core upper part mechanism 10 including a control rod drive mechanism can be lifted in the cask 9 (see FIG. 1). This is because when the upper core mechanism 10 is in the normal position it interferes with the fuel exchange, so lift it up to a place where it does not interfere, and after the refueling work is completed, return the upper core mechanism 10 to the regular position again. .

第3−A図において、実線で示した滑車3と点線で示し
た滑車3とを近接させることで、両滑車3,3間で懸垂保
持されるホールドダウンチューブ4位置を無端レール2
に近接させている状態を示している。このような状態で
待機させておけば、炉心上部機構10が正規の位置を占め
るときであっても、何等支障ないことが理解されよう。
燃料交換を行なう際、先ず炉心上部機構10をキャスク9
内に持ち上げることについては既述したとおりである。
燃料交換時における2個の滑車3,3、ホールドダウンチ
ューブ4および錘付きグリッパ5の操作については、こ
れ迄の説明で明らかと考えるが、念の為、以下に簡単に
述べておく。ホールドダウンチューブ4が2個の滑車3,
3の中点にある関係を維持せしめて、第3−A図の中心
Oにあったホールドダウンチューブ4をA点に移動させ
るには、A点までの距離aを計算し、半径をrとする
と、2個の滑車3,3間の距離が 2√r2−a2となるように、チェーン巻取装置6,6を作動
して一方の滑車3を移動させ、滑車3とホールドダウン
チューブ4間の距離が√r2−a2となるように、チェーン
巻取装置6a,6aを作動してホールドダウンチューブ4を
移動させる。また、一方の滑車3を固定させておき、第
3−B図のB点に移動させるには、移動角度θと、固定
の滑車3からB点までの距離を計算し、上記したところ
に準じて、他方の滑車3を角度θ分移動させ、ホールド
ダウンチューブ4を所定長分移動させればよい。このよ
うにして炉心構成要素の上部位置を占めた錘付きグリッ
パ5は、チェーン巻取装置6bの作動によって降下上昇
し、燃料集合体等をつかんで搬送することができる。
In FIG. 3-A, by bringing the pulley 3 shown by the solid line and the pulley 3 shown by the dotted line close to each other, the position of the holddown tube 4 suspended and held between the pulleys 3 and 3 is changed to the endless rail 2.
It shows the state of being close to. It will be understood that if the core upper part mechanism 10 occupies the normal position by standing by in such a state, no trouble will occur.
At the time of refueling, first the core upper mechanism 10
Lifting inside is as described above.
The operation of the two pulleys 3, 3, the holddown tube 4, and the weighted gripper 5 at the time of refueling is considered to be clear in the above description, but for the sake of caution, it will be briefly described below. Holddown tube 4 has two pulleys 3,
To move the holddown tube 4 located at the center O in FIG. 3-A to the point A while maintaining the relationship at the midpoint of 3, calculate the distance a to the point A and set the radius to r. Then, the chain winding devices 6 and 6 are operated to move the one pulley 3 so that the distance between the two pulleys 3 and 3 becomes 2√r 2 −a 2, and the pulley 3 and the hold down tube are moved. The hold-down tube 4 is moved by operating the chain winding devices 6a and 6a so that the distance between the four becomes √r 2 −a 2 . Further, in order to move one pulley 3 to the point B in FIG. 3-B with one pulley 3 fixed, the moving angle θ and the distance from the fixed pulley 3 to the point B are calculated, and according to the above, Then, the other pulley 3 may be moved by the angle θ and the hold down tube 4 may be moved by a predetermined length. The weighted gripper 5 occupying the upper position of the core component in this way can be lowered and raised by the operation of the chain winding device 6b, and can grasp and transport the fuel assembly or the like.

<発明の効果> この発明によれば、固定蓋7の重量は従来の回転プラグ
が大重量物であったのと比較すれば顕著に軽量化できる
し、回転プラグのように廻す必要がないので、原子炉構
造を簡略,小型にするうえで甚だ有効である。熱遮蔽,
放射線遮蔽は原子炉容器1の外側で行なうことになる
が、ホットセル方式のように燃料交換に際して原子炉蓋
を取外さなくてよいから、遮蔽セルは小さなもので済
む。しかも錘付きグリッパ5を有するホールドダウンチ
ューブ4は原子炉容器1の内周面に沿って設けた無端レ
ール2上の2個の滑車3,3間に懸垂保持したから、それ
ら2個の滑車3,3を近づけることによって原子炉容器1
内面に近接した位置をホールドダウンチューブ4の待機
位置とすることができ、炉心上部機構10が正規の位置を
占めても何等邪魔にはならない。そして、燃料交換のと
きは炉心上部機構10をキャスク9内に持ち上げて燃料交
換に必要なスペースを形成しさえすれば、あとはチェー
ン巻取装置6,6a,6bを適宜操作することで錘付きグリッ
パ5を炉内のどの位置にも移動でき、燃料交換できる点
で甚だ優れている。
<Effects of the Invention> According to the present invention, the weight of the fixed lid 7 can be remarkably reduced as compared with a conventional rotary plug that is heavy, and it is not necessary to rotate it like a rotary plug. It is extremely effective in simplifying and downsizing the reactor structure. Heat shield,
Although radiation shielding is performed outside the reactor vessel 1, it is not necessary to remove the reactor lid at the time of refueling as in the hot cell system, and thus the shielding cell can be small. Moreover, since the holddown tube 4 having the gripper 5 with a weight is suspended and held between the two pulleys 3 and 3 on the endless rail 2 provided along the inner peripheral surface of the reactor vessel 1, these two pulleys 3 , 3 by bringing the reactor vessel 1 closer
A position close to the inner surface can be set as the standby position of the hold-down tube 4, and even if the core upper part mechanism 10 occupies the regular position, it does not disturb anything. At the time of refueling, the upper core mechanism 10 is lifted into the cask 9 to form a space required for refueling, and then the chain winding devices 6, 6a, 6b are appropriately operated to attach the weight. It is extremely excellent in that the gripper 5 can be moved to any position in the furnace and the fuel can be exchanged.

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

第1図はこの発明になる原子炉用燃料交換装置の原理を
理解さすための説明図、第2−A図は無端レール部分の
斜視図、第2−B図はホールドダウンチューブとその内
側にある錘付きグリッパの関係を示す断面図、第2−C
図は滑車部分の斜視図、第3−A図と第3−B図は2個
の滑車と錘付きグリッパの移動を説明するための平面図
である。 1…原子炉容器、2…無端レール、3…滑車、4…ホー
ルドダウンチューブ、5…錘付きグリッパ、6,6a,6b…
チェーン巻取装置、7…固定蓋、8…密閉カバー、9…
キャスク、10…炉心上部機構。
FIG. 1 is an explanatory view for understanding the principle of a fuel exchange device for a reactor according to the present invention, FIG. 2-A is a perspective view of an endless rail portion, and FIG. 2-B is a holddown tube and its inside. Sectional view showing a relation between certain weighted grippers, 2-C
The figure is a perspective view of the pulley portion, and FIGS. 3-A and 3-B are plan views for explaining the movement of the two pulleys and the gripper with a weight. 1 ... Reactor vessel, 2 ... Endless rail, 3 ... Pulley, 4 ... Hold down tube, 5 ... Gripper with weight, 6, 6a, 6b ...
Chain winding device, 7 ... Fixed lid, 8 ... Sealing cover, 9 ...
Cask, 10 ... Upper core mechanism.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】原子炉容器(1)の上部内周面に設けた無
端レール(2)に2個の滑車(3)(3)を滑動自在に
係合し、それら2個の滑車(3)(3)間で錘付きグリ
ッパ(5)を内側に有するホールドダウンチューブ
(4)を懸垂保持し、無端レール(2)上での各滑車
(3)(3)の移動用、2個の滑車(3)(3)間での
ホールドダウンチューブ(4)の移動用、および錘付き
グリッパ(5)の昇降用の各チェーン巻取装置(6)
(6a)(6b)を、原子炉容器(1)の頂部を密封する固
定蓋(7)に取付けた密閉カバー(8)内に装着すると
共に、固定蓋(7)にキャスク(9)を形成し、炉心上
部機構(10)をキャスク(9)内に持ち上げ可能とした
ことを特徴とする原子炉用燃料交換装置。
1. Two pulleys (3) and (3) are slidably engaged with an endless rail (2) provided on an inner peripheral surface of an upper portion of a reactor vessel (1), and the two pulleys (3) are attached. ) (3) for suspending and holding a holddown tube (4) having a weighted gripper (5) inside, and for moving each pulley (3) (3) on an endless rail (2), two pieces Each chain winding device (6) for moving the holddown tube (4) between the pulleys (3) (3) and for lifting the weighted gripper (5)
(6a) and (6b) are mounted in a closed cover (8) attached to a fixed lid (7) that seals the top of the reactor vessel (1), and a cask (9) is formed on the fixed lid (7). A reactor fuel exchange device, characterized in that the upper core mechanism (10) can be lifted into the cask (9).
JP61265561A 1986-11-10 1986-11-10 Refueling device for nuclear reactor Expired - Lifetime JPH0679072B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61265561A JPH0679072B2 (en) 1986-11-10 1986-11-10 Refueling device for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61265561A JPH0679072B2 (en) 1986-11-10 1986-11-10 Refueling device for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS63120295A JPS63120295A (en) 1988-05-24
JPH0679072B2 true JPH0679072B2 (en) 1994-10-05

Family

ID=17418819

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61265561A Expired - Lifetime JPH0679072B2 (en) 1986-11-10 1986-11-10 Refueling device for nuclear reactor

Country Status (1)

Country Link
JP (1) JPH0679072B2 (en)

Also Published As

Publication number Publication date
JPS63120295A (en) 1988-05-24

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