JPS5937497A - Nuclear fuel transporting facility - Google Patents

Nuclear fuel transporting facility

Info

Publication number
JPS5937497A
JPS5937497A JP57147329A JP14732982A JPS5937497A JP S5937497 A JPS5937497 A JP S5937497A JP 57147329 A JP57147329 A JP 57147329A JP 14732982 A JP14732982 A JP 14732982A JP S5937497 A JPS5937497 A JP S5937497A
Authority
JP
Japan
Prior art keywords
fuel
packet
fuel transfer
reactor
chute
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
JP57147329A
Other languages
Japanese (ja)
Inventor
隆 井上
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
Fuji Electric Manufacturing 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, Fuji Electric Manufacturing Co Ltd filed Critical Fuji Electric Co Ltd
Priority to JP57147329A priority Critical patent/JPS5937497A/en
Publication of JPS5937497A publication Critical patent/JPS5937497A/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

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  • Control Of Conveyors (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】 この発明は、液体金属冷却型高速増殖炉において、原子
炉容器と炉外燃料貯蔵槽との間で新燃料および使用済燃
料の移送を行う燃料移送設備に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a fuel transfer facility for transferring new fuel and spent fuel between a reactor vessel and an extra-core fuel storage tank in a liquid metal cooled fast breeder reactor.

頭記の燃料移送設備は、N子炉の燃料交換に用いられる
ものであり、原子炉の稼働率の向上を図るためにも、で
きるだけ短時間で能率よく燃料の移送が行えること、か
つその取扱い、保守点検等が容易に行えることが望まれ
る。
The above mentioned fuel transfer equipment is used for fuel exchange in N sub-reactors, and in order to improve the operating rate of the reactor, it must be possible to transfer fuel efficiently in the shortest possible time and its handling. It is desirable that maintenance and inspection can be easily performed.

この種の装置として9M子炉容器と炉外燃料貯蔵槽(以
下1”EVSTJと呼称する)の燃料出し入れを斜道シ
ュート方式で行うとともに、両容器の間を燃料移送セル
で結び、このセル内に燃料移送機を走行させることによ
り、炉心から取出した使用済燃料および新燃料を燃料パ
ケットに入れた上でシュートを通じてそれぞれ原子炉容
器とEVSTとの間で移送するようにしたものが従来知
られている。このように斜道式シュートを用いることに
より、燃料の取扱いを鉛直に吊り下げて行う原子炉容器
内の燃料交換機と前記の燃料移送機とが互に干渉し合う
ことがなく、パケットヲ介して燃料の受は渡しが行える
。したがって以前の装置で使用されていた炉内の燃料中
継装置が省略でき、それだけ設備が簡略となる利点が得
られる。しかし一方では、前述のような燃料移送セル内
で移送を行う方式では、次記のような難点がある。すな
わち、燃料移送セルの内部は、シュートを通じて原子炉
容器内と連通し合っており、−次冷却材として使用され
ている放射化したナトリウムがセル内に滴下堆積してい
たり、炉内側のカバーガスが侵入するので放射能汚染区
域となっている。このためにセルには十分な気密機能お
よび使用済燃料および上記放射能に対するじゃへい機能
が要求される。
In this type of equipment, fuel is taken in and out of the 9M sub-reactor vessel and the extra-core fuel storage tank (hereinafter referred to as 1"EVSTJ) using an inclined chute method, and a fuel transfer cell is connected between the two vessels, and inside this cell Conventionally known systems have been known in which spent fuel and new fuel taken out of the reactor core are put into fuel packets and transferred between the reactor vessel and the EVST through chutes by running a fuel transfer machine. By using the slope type chute in this way, the fuel exchange machine inside the reactor vessel, which handles fuel by hanging vertically, and the above-mentioned fuel transfer machine do not interfere with each other, and the packets can be easily handled. Therefore, the fuel relay device inside the reactor that was used in the previous system can be omitted, which has the advantage of simplifying the equipment.However, on the other hand, the fuel transfer as mentioned above The method of transferring fuel inside the cell has the following disadvantages: The inside of the fuel transfer cell is communicated with the inside of the reactor vessel through a chute, and the radiation used as secondary coolant is The cell is a radioactively contaminated area due to dripping accumulation of oxidized sodium and infiltration of the cover gas from inside the reactor.For this reason, the cell has sufficient airtightness and is equipped with sufficient airtightness to prevent spent fuel and the above radioactivity. Jahei function is required.

この結果としてセルは厚い重コンクリート製の大形の重
量構築物となり、かつ耐震性の問題もあって設備費が非
常に高くなる。またセル内には保守要員が立ち入ること
ができないため、セル内に据付けた移送機およびその付
属機器等の保守点検。
As a result, the cell becomes a large, heavy structure made of thick, heavy concrete, and there are also problems with earthquake resistance, resulting in extremely high equipment costs. In addition, since maintenance personnel are not allowed to enter the cell, maintenance and inspection of the transfer machine installed inside the cell and its attached equipment, etc.

補修などは全てセル内でマニプレータ等による外部から
の遠隔操作で行わなければならず、メンテナンス性が悪
い。
All repairs must be performed inside the cell by remote control from the outside using a manipulator or the like, resulting in poor maintainability.

この発明は、上記の点にかんがみなされたものであり、
その目的は従来における斜道シュート・セル方式の難点
を解消し、設備費が安価で、しかも構成機器の保守点検
等のメンテナンスが容易に行える新規な燃料移送設備を
提供することにある。
This invention has been made in view of the above points,
The purpose is to provide a new fuel transfer facility that eliminates the drawbacks of the conventional inclined chute cell system, has low equipment costs, and allows easy maintenance such as maintenance and inspection of component equipment.

以下この発明の構成並びに運転動作を図示実施例ζこ基
づいて詳述する。
The configuration and operation of the present invention will be described in detail below based on illustrated embodiments.

まず第1図および第2図により、設備全体の概要を述べ
る。図において、lは鋼製の原子炉格納容器、2は格納
容器1の床面下に設置された原子炉容器、3は炉心、4
は原子炉容器の回転プラグ5の上に据付けられた燃料交
換機、6は格納容器1の外部に据付けられた炉外燃料貯
蔵槽(睨″ST)。
First, an overview of the entire equipment will be described with reference to Figures 1 and 2. In the figure, l is a steel reactor containment vessel, 2 is a reactor vessel installed under the floor of the containment vessel 1, 3 is a reactor core, and 4
6 is a fuel exchanger installed on the rotary plug 5 of the reactor vessel, and 6 is an ex-core fuel storage tank (ST) installed outside the containment vessel 1.

7はその槽内に据付けられた燃料収納ラック、8はその
燃料取扱機を示す。ここまでの原子炉施設は従来からの
ものと同様である。
Reference numeral 7 indicates a fuel storage rack installed in the tank, and reference numeral 8 indicates the fuel handling machine. The nuclear reactor facilities up to this point are the same as conventional ones.

さてこの発明により、原子炉容器2およびEVST6の
内外にまたがる燃料出入通路として、まず格納容器1と
原子炉容器2との間、および格納容器とFiVST 6
との間にはそれぞれ独立して上端ボートが格納容器内の
床面上に開口する斜道式の燃料出入シュート9と10が
構成されている。このうちシュート9は原子炉容器2の
固定プラグを貫通。
Now, according to the present invention, as a fuel inlet/outlet passage extending between the inside and outside of the reactor vessel 2 and the EVST 6, firstly, the passage between the containment vessel 1 and the reactor vessel 2, and between the containment vessel and the FiVST 6.
There are constructed ramp-type fuel inlet/output chutes 9 and 10, each of which has an upper end boat that independently opens onto the floor surface of the containment vessel. Of these, chute 9 penetrates the fixed plug of reactor vessel 2.

して直接床面上にボート開口し、一方のシュートlOは
EVST 6の槽壁環よび格納容器lを貫通して床面上
に開口するようこと構成されており、かつ各シュー)9
.10の上端ボートには床ドアバルブ11j12が接続
しである。なお、シュート10に対してはシュートを包
囲してしやへい体13が構築しである。一方、格納容器
lの内部には、前 5− 記シュート9とlOのボートの間を結ぶ燃料移送経路l
こ沿って走行レール14が敷設されており。
One chute (10) is configured to penetrate the tank wall ring of the EVST 6 and the containment vessel (1) and open onto the floor, and each shoe (9)
.. A floor door valve 11j12 is connected to the upper end boat 10. Incidentally, for the chute 10, a flexible body 13 is constructed to surround the chute. On the other hand, inside the containment vessel l, there is a fuel transfer path l connecting the chute 9 and the boat lO mentioned above.
A traveling rail 14 is laid along this line.

このレール上に詳細構造を後述する走行台車式燃料移送
機15が配備しである。才た核燃料移送機15の走行経
路に沿ってその経路の途中には符号16で示す移送構保
守点検用ピット、および符号17で示す燃料収納パケッ
トの切離し用ビットが床面下に構成されている。
A traveling trolley type fuel transfer machine 15, the detailed structure of which will be described later, is disposed on this rail. Along the running route of the nuclear fuel transfer device 15, a pit for maintenance and inspection of the transfer structure, indicated by reference numeral 16, and a bit for separating the fuel storage packet, indicated by reference numeral 17, are constructed under the floor. .

次に第3図ないし第6図により1台車式燃料移送機15
の詳細構造について説明する。すなわち移送機15は、
走行レール14の上を走行する自走式台車16に密閉形
のコフィン18を塔載しており、かつコ\フィンはその
下端にドアバルブ19を、頂部には次記の燃料収納パケ
ットを昇降操作する駆動部20を備え、該駆動部20に
チェーンあるいはテープ20Aを介して燃料収納パケッ
ト21を吊り下げ、コフィン内に収容するように構成さ
れている。このファイン五8は図示のように十分な厚さ
のしゃへい体18Aで包囲されている。
Next, as shown in Figures 3 to 6, the one-truck type fuel transfer machine 15
The detailed structure of is explained below. That is, the transfer machine 15 is
A closed coffin 18 is mounted on a self-propelled cart 16 that runs on a traveling rail 14, and the coffin has a door valve 19 at its lower end and a fuel storage packet as described below at its top for lifting and lowering operations. A fuel storage packet 21 is suspended from the drive unit 20 via a chain or tape 20A, and is housed in the coffin. As shown in the figure, the fine 58 is surrounded by a shield 18A of sufficient thickness.

またパケット21は上面を開放した2本の燃料収 6− 納ポット21Aと21Bで構成されており、かつその上
下には車輪2ICを備えコフィン18内に上下方向に敷
設した左右のガイドレール18Bにガイド支持されてい
る。一方、燃料出入シュート9は第3図および第7図に
示すように、その斜道に沿って前記パケット21をガイ
ドするガイドレール9Aが敷設されている。なお9Bは
しやへい体である。この構造はEVST側のシュー)1
0についても同様である。また第8図に示すように原子
炉容器内には、燃料交換機の移動軌跡22に沿ってシュ
ート9の終端正こ並んで4本の燃料中継ラック23A〜
23Dが配備されている。
In addition, the packet 21 is composed of two fuel storage pots 21A and 21B with open tops, and wheels 2IC are provided above and below the fuel storage pots 21A and 21B. Guide supported. On the other hand, as shown in FIGS. 3 and 7, the fuel inlet/outlet chute 9 is provided with a guide rail 9A that guides the packet 21 along its slope. Note that 9B is a cylindrical body. This structure is the shoe on the EVST side)1
The same applies to 0. In addition, as shown in FIG. 8, there are four fuel relay racks 23A to 4 in parallel with the end of the chute 9 along the movement locus 22 of the refueling machine in the reactor vessel.
23D is deployed.

次に上記構成の設備における燃料移送動作ζこついて述
べる。まず、燃料移送機15をEVS T側シュート1
0の上端ボート位置へ移し、ここでドアパルプ19と1
2を接続した上で開き、この状態でパケット21をシュ
ー)10を通じてEVST 6の槽内へ吊り降ろす。こ
こで燃料取扱機8を駆動シ、予めEVST内に搬入され
ている新燃料を・くケラ1−21の2本のボッ)21A
、21Bへ挿入する。この間に原子炉容器側では、燃料
交換機4を駆動して炉心3から使用済燃料を引き抜き、
第8図に示した炉内の中継シック23Aおよび23Dへ
黒丸27で示ように挿入して待機し、炉外搬出移送の準
備を整えておく。次いでl1iVST側では。
Next, the fuel transfer operation ζ in the equipment with the above configuration will be described. First, move the fuel transfer device 15 to the EVST T side chute 1.
0 to the upper end boat position, and here door pulp 19 and 1
2 is connected and opened, and in this state, the packet 21 is suspended into the tank of the EVST 6 through the shoe 10. Here, the fuel handling machine 8 is driven, and the new fuel that has been brought into the EVST in advance is loaded into the two cylinders (1-21) 21A.
, 21B. During this time, on the reactor vessel side, the fuel exchanger 4 is driven to pull out the spent fuel from the reactor core 3.
They are inserted into the relay chics 23A and 23D in the furnace shown in FIG. 8 as indicated by black circles 27 and are on standby, ready for transport outside the furnace. Next, on the l1iVST side.

新燃料を収容したバケツ)21をシュート10を通じて
引き上げ移送機15のコフィン18内lこ引き込み、更
にドアパルプ19および12を閉じた上で両者の接続を
切り離す。次に移送機15をレールi4上を走行させ1
反対側のシュート9の位置まで移動し、この位置でドア
パルプ19と11を接続した上で開く。そして新燃料を
収容したパケット21をシュー!・9内に吊り降ろし、
その終端に達したところで、今度は燃料交換機4を操作
し1才ず第8図の矢印(イ)、 (1:I)のように白
丸の新燃料28をパケット21のポット21A、21B
から炉内中継ラック23B・23Cへ移し替え1次いで
ラック23A、23Dから矢印そ・)、←)のようζこ
黒丸の使用済燃料27を空になったパケットのボッl−
21A、21DJこ挿入する。この作業が終了すれば、
直ちにパケット21は移送機15のコフィン五8の中へ
吊り上げ収容され、更にドアノ(ルブ19と11を閉じ
て両者を切り離す。その後に移送機15を再びEVST
側のシュート10まで移動し、ドアパルプ19と12と
を接続した上でシュー)10を通じてパケット21をE
VSTの槽内に吊り降し1次いで燃料取扱機8の操作に
より使用済燃料をパケット21から貯蔵ラック7へ移し
替える。この間に原子炉側では、燃料交換機4が新燃料
をラック23B、23Cから取り出して炉心3へ装荷す
る。これで燃料移送の1サイクルの工程が終了し、以下
同様なサイクルを繰返えして多くの新燃料および使用済
燃料をEVST 6と原子炉容器2との間で移し替えな
がら燃料交換を行う。なお、燃料バケツ)21の2本の
ポットのうち一方を新燃料専用、他方を使用済燃料専用
として1本ずつ燃料移送を行うこともでき、この方式に
よれば炉内ラック23A〜23Dは無くてもよい。
The bucket) 21 containing fresh fuel is pulled up through the chute 10 into the coffin 18 of the transfer machine 15, and the door pulps 19 and 12 are closed, and the connection between them is severed. Next, the transfer machine 15 is run on the rail i4 and
Move to the chute 9 position on the opposite side, connect the door pulps 19 and 11 at this position, and then open it. Then, shoot the packet 21 containing the new fuel!・Hang down inside 9,
When it reaches the end, operate the fuel exchanger 4 and pour new fuel 28 into the pots 21A and 21B of the packet 21 as shown by the arrows (A) and (1:I) in Figure 8.
Transfer the spent fuel 27 from the racks 23A and 23D to the in-furnace relay racks 23B and 23C as shown by the arrows ) and ←) in the empty packet bottles.
Insert 21A and 21DJ. Once this work is completed,
Immediately, the packet 21 is hoisted up and stored in the coffin 58 of the transfer machine 15, and the doorknobs (lubs 19 and 11 are closed to separate the two).Then, the transfer machine 15 is moved to the EVST again.
Move to the chute 10 on the side, connect the door pulps 19 and 12, and then feed the packet 21 through the shoe 10.
The spent fuel is suspended into the VST tank and then transferred from the packet 21 to the storage rack 7 by operating the fuel handling machine 8. During this time, on the reactor side, the fuel exchanger 4 takes out new fuel from the racks 23B and 23C and loads it into the reactor core 3. This completes one cycle of fuel transfer, and the same cycle is repeated to perform fuel exchange while transferring a large amount of new fuel and spent fuel between EVST 6 and reactor vessel 2. . In addition, it is also possible to transfer fuel one by one by setting one of the two pots in the fuel bucket (21) exclusively for new fuel and the other exclusively for spent fuel. According to this method, there are no in-reactor racks 23A to 23D. You can.

次に燃料移送機15の本体および燃料ノ(ケラト 9− 21の保守点検の方法について説明する。第1図−2第
2図に示した二つのビット16.17の詳細構造は第9
図に示すごとくであり、このうち特にパケット切離し用
ビット17にはその上部に床ドアパルプ17Aを、更に
ビット内にはパケット切離し装置24およびパケット収
容キャスク25を備えており、かつキャスク25は必要
によりバケツ)21を収容して外部のメンテナンス施設
へ搬出できるようにしである。また移送機本体点検用ピ
ッ)16の中には保守要員が直接立ち入ることができる
ようにされ、かつビット内にはドアパルプ19の洗浄2
分解点検に必要な保守設備26を備えている。そして移
送機15の保守点検は、まず移送機】5をビット17の
真上に移動し、ドアパルプ19と17Aとを接続した状
態でナトリウムが入っているパケット21をキャスク2
5内に吊り降し、次いでバケツl−21、!:吊り下げ
テープ20との間を切離す。次に移送機15をピッ)1
6まで駆動し、ここで移送機本体を十分洗浄した上でド
アパルプ19等の分解点検を行う。この作業は−10− 保守要員が接近して直接行うようにする。
Next, the method of maintenance and inspection of the main body of the fuel transfer device 15 and the fuel nozzle 9-21 will be explained.The detailed structure of the two bits 16 and 17 shown in Figs.
As shown in the figure, the packet separating bit 17 in particular is equipped with a floor door pulp 17A on its upper part, and furthermore a packet separating device 24 and a packet accommodation cask 25 inside the bit, and the cask 25 is provided as necessary. It is designed to accommodate the bucket) 21 and transport it to an external maintenance facility. In addition, maintenance personnel can directly enter the inspection pit (16) for the main body of the transfer machine, and the inside of the bit (for cleaning the door pulp 19)
It is equipped with maintenance equipment 26 necessary for disassembly and inspection. Maintenance and inspection of the transfer machine 15 is carried out by first moving the transfer machine 5 directly above the bit 17, and with the door pulp 19 and 17A connected, the packet 21 containing sodium is transferred to the cask 2.
5, then bucket l-21,! : Separate from the hanging tape 20. Next, pick the transfer machine 15)1
6, and after thoroughly cleaning the main body of the transfer machine, the door pulp 19 and the like are disassembled and inspected. This work should be carried out directly by maintenance personnel.

上述のようにこの発明によりば、斜道式燃料出入シュー
トとコフィンを塔載した走行台車式燃料移送機とを組合
わせて燃料移送設備を構成したので、斜道シュートによ
る燃料出入方式の特長を十分活かして能率よく短時間で
燃料の出し入れ・移送が行えるとともに、一方では従来
のような大形重量構築物の燃料移送セルが不要となるの
で、設備費が安価となる。更に、頻繁な保守点検を必要
とする燃料移送機のメンテナンス作業を従来のようなマ
ンプレータの遠隔操作によらず、保守要員が燃料移送機
に接近して直接作業を行うことができてメンテナンス性
を大巾に改善できる等の効果が得られる。
As described above, according to the present invention, the fuel transfer equipment is constructed by combining the inclined fuel inlet/output chute and the traveling trolley type fuel transfer machine equipped with a coffin. Not only can fuel be fully utilized and efficiently loaded and transferred in a short period of time, but on the other hand, there is no need for a conventional large, heavy-structured fuel transfer cell, resulting in lower equipment costs. Furthermore, maintenance work on the fuel transfer machine, which requires frequent maintenance and inspection, can be performed directly by approaching the fuel transfer machine, rather than by remote control of a manual operator as in the past, which improves maintenance efficiency. Effects such as significant improvements can be obtained.

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

各図はこの発明の実施例を示すものであり、第1図は設
備全体の概要を示す構成配置図、第2図は第1図の一部
平面図、第3図は燃料移送機および原子炉容器側のシュ
ートの詳細構造を示す縦断面図、第4図は燃料移送機の
正面外形図、第5図は第3図の矢視v−■断面図、第6
図は燃料パケットの正面外形図、第7図は第3図の矢視
■−■断面図、第8図は炉内における燃料移し替えの動
作説明図、第9図は燃料移送機の保守点検用設備の構成
配置図である。 l・・・原子炉格納容器、2・・・原子炉容器、3・・
・炉心、4・・・燃料交換機、6・・・炉外燃料貯蔵槽
、7・・・燃料貯蔵ラック、8・・・燃料取扱機、9.
10・・・斜道式燃料出入シュー)、11.12・・・
床ドアパルプ、14・・・走行レール、15・・・走行
台車式燃料移送機、16・・・燃料移送機本体の保守点
検用ピット。 17・・・燃料パケット切離し用ビット、18・・・コ
フィン、19・・・ドアパルプ、20・・・パケット昇
降駆才4医 オ、5図 76図 す1
Each figure shows an embodiment of the present invention. Figure 1 is a configuration diagram showing an outline of the entire equipment, Figure 2 is a partial plan view of Figure 1, and Figure 3 shows a fuel transfer machine and an atom. A vertical cross-sectional view showing the detailed structure of the chute on the reactor vessel side, Fig. 4 is a front external view of the fuel transfer device, Fig. 5 is a cross-sectional view taken along arrow v-■ in Fig. 3, and Fig. 6
The figure is a front external view of the fuel packet, Figure 7 is a sectional view taken along the arrow ■-■ in Figure 3, Figure 8 is an explanatory diagram of the operation of fuel transfer in the reactor, and Figure 9 is a maintenance and inspection of the fuel transfer machine. FIG. l...Reactor containment vessel, 2...Reactor vessel, 3...
- Core, 4... Fuel exchange machine, 6... Ex-core fuel storage tank, 7... Fuel storage rack, 8... Fuel handling machine, 9.
10... Slope type fuel inlet/out shoe), 11.12...
Floor door pulp, 14... Traveling rail, 15... Traveling trolley type fuel transfer machine, 16... Pit for maintenance and inspection of fuel transfer machine body. 17...Fuel packet separation bit, 18...Coffin, 19...Door pulp, 20...Packet lifter 4 doctor, 5 Figure 76 Figure 1

Claims (1)

【特許請求の範囲】 l)原子炉格納容器内の床面上に上端ボートを開口して
それぞれ床面下の原子炉容器および炉外燃料貯蔵槽との
間を結んで構成された斜道式の燃料出入シュートと、前
記各シュートの上端ボートに設置された床ドアバルブと
、双方のシュートのボートとの間を結ぶ燃料移送経路に
沿って格納容器の床面上に敷設された走行レールと、燃
料パケット、パケットをチェーンあるいはテープで吊り
下げて昇降操作するパケット昇降駆動機構およびドアパ
ルプを装備したコフィンを走行台車に塔載して前記レー
ル上を走行する走行台車式燃料移送機とからなり、前記
燃料移送機の運転操作により原子炉容器と炉外燃料貯蔵
槽との間で新燃料および使用済燃料の移送を行うことを
特徴とする原子炉の燃料移送設備。 2、特許請求の範囲第1項記載の燃料移送設備において
、燃料パケットが各ポットごとに燃料を1本ずつ収納す
る複数の燃料ポットで構成されていることを4!徴とす
る原子炉の燃料移送設備。 3)I¥j#v−請求の範囲第1項記載の燃料移送設備
において、走行台車式燃料移送機の走行経路に沿って、
格納容器の床面下に燃料パケット切離し用ビットおよび
燃料移送機本体の保守点検用ビットを備えていることを
特徴とする原子炉の燃料移送設備。
[Scope of Claims] l) A slope type structure in which an upper end boat is opened above the floor surface of the reactor containment vessel and is connected to the reactor vessel and the external fuel storage tank below the floor surface. a fuel inlet/output chute, a floor door valve installed on the upper end boat of each chute, and a running rail laid on the floor surface of the containment vessel along a fuel transfer path connecting the boats of both chutes; The fuel packet includes a fuel packet, a packet lifting/lowering drive mechanism for lifting and lowering the packet by suspending the packet with a chain or tape, and a traveling trolley type fuel transfer machine for mounting a coffin equipped with a door pulp on a traveling trolley and traveling on the rail, Fuel transfer equipment for a nuclear reactor, characterized in that new fuel and spent fuel are transferred between a reactor vessel and an external fuel storage tank by operating a fuel transfer device. 2. In the fuel transfer equipment according to claim 1, the fuel packet is composed of a plurality of fuel pots each storing one bottle of fuel. 4! This is a characteristic nuclear reactor fuel transfer facility. 3) I\j#v-In the fuel transfer equipment according to claim 1, along the travel route of the traveling trolley type fuel transfer machine,
1. Fuel transfer equipment for a nuclear reactor, comprising a bit for separating fuel packets and a bit for maintenance and inspection of a fuel transfer device body under the floor of a containment vessel.
JP57147329A 1982-08-25 1982-08-25 Nuclear fuel transporting facility Pending JPS5937497A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57147329A JPS5937497A (en) 1982-08-25 1982-08-25 Nuclear fuel transporting facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57147329A JPS5937497A (en) 1982-08-25 1982-08-25 Nuclear fuel transporting facility

Publications (1)

Publication Number Publication Date
JPS5937497A true JPS5937497A (en) 1984-02-29

Family

ID=15427715

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57147329A Pending JPS5937497A (en) 1982-08-25 1982-08-25 Nuclear fuel transporting facility

Country Status (1)

Country Link
JP (1) JPS5937497A (en)

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS63198052A (en) * 1987-02-13 1988-08-16 Fuji Photo Film Co Ltd Method for processing silver halide color photographic sensitive material
JPS63202744A (en) * 1987-02-19 1988-08-22 Fuji Photo Film Co Ltd Silver halide color photographic sensitive material
JPS63301947A (en) * 1987-01-27 1988-12-08 Fuji Photo Film Co Ltd Silver halide color photographic sensitive material
JPS64551A (en) * 1987-03-25 1989-01-05 Fuji Photo Film Co Ltd Silver halide color photographic sensitive material and method for processing same
JPH0235451A (en) * 1988-07-26 1990-02-06 Fuji Photo Film Co Ltd Color photosensitive material
JPH0264633A (en) * 1988-08-31 1990-03-05 Fuji Photo Film Co Ltd Thermodevelopable color photosensitive material and image forming method therewith
JPH0353247A (en) * 1989-07-21 1991-03-07 Fuji Photo Film Co Ltd Silver halide color photographic sensitive material
JP2014219411A (en) * 2013-05-08 2014-11-20 ジームペルカンプ・ヌクレアールテヒニーク・ゲゼルシャフト・ミト・ベシュレンクテル・ハフツング Carrying device for carrying fuel element
JP2014219412A (en) * 2013-05-08 2014-11-20 ジームペルカンプ・ヌクレアールテヒニーク・ゲゼルシャフト・ミト・ベシュレンクテル・ハフツング Carrying device for carrying fuel element
WO2024192095A1 (en) * 2023-03-15 2024-09-19 Westinghouse Electric Company Llc Inclined fuel transfer system between containment and fuel handling building

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS63301947A (en) * 1987-01-27 1988-12-08 Fuji Photo Film Co Ltd Silver halide color photographic sensitive material
JPS63198052A (en) * 1987-02-13 1988-08-16 Fuji Photo Film Co Ltd Method for processing silver halide color photographic sensitive material
JPS63202744A (en) * 1987-02-19 1988-08-22 Fuji Photo Film Co Ltd Silver halide color photographic sensitive material
JPS64551A (en) * 1987-03-25 1989-01-05 Fuji Photo Film Co Ltd Silver halide color photographic sensitive material and method for processing same
JPH0235451A (en) * 1988-07-26 1990-02-06 Fuji Photo Film Co Ltd Color photosensitive material
JPH0264633A (en) * 1988-08-31 1990-03-05 Fuji Photo Film Co Ltd Thermodevelopable color photosensitive material and image forming method therewith
JPH0353247A (en) * 1989-07-21 1991-03-07 Fuji Photo Film Co Ltd Silver halide color photographic sensitive material
JP2014219411A (en) * 2013-05-08 2014-11-20 ジームペルカンプ・ヌクレアールテヒニーク・ゲゼルシャフト・ミト・ベシュレンクテル・ハフツング Carrying device for carrying fuel element
JP2014219412A (en) * 2013-05-08 2014-11-20 ジームペルカンプ・ヌクレアールテヒニーク・ゲゼルシャフト・ミト・ベシュレンクテル・ハフツング Carrying device for carrying fuel element
WO2024192095A1 (en) * 2023-03-15 2024-09-19 Westinghouse Electric Company Llc Inclined fuel transfer system between containment and fuel handling building

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