JPH0334836B2 - - Google Patents

Info

Publication number
JPH0334836B2
JPH0334836B2 JP60120872A JP12087285A JPH0334836B2 JP H0334836 B2 JPH0334836 B2 JP H0334836B2 JP 60120872 A JP60120872 A JP 60120872A JP 12087285 A JP12087285 A JP 12087285A JP H0334836 B2 JPH0334836 B2 JP H0334836B2
Authority
JP
Japan
Prior art keywords
fuel
bucket
liquid metal
sodium
liquid
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
JP60120872A
Other languages
Japanese (ja)
Other versions
JPS61278796A (en
Inventor
Hiroshi Ozaki
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 JP60120872A priority Critical patent/JPS61278796A/en
Publication of JPS61278796A publication Critical patent/JPS61278796A/en
Publication of JPH0334836B2 publication Critical patent/JPH0334836B2/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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Jet Pumps And Other Pumps (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)

Description

【発明の詳細な説明】 〔発明の属する技術分野〕 本発明は、特に高速増殖炉において、原子炉燃
料を容器内に収納し燃料出入機により不活性ガス
雰囲気内にて、原子炉容器と炉外燃料中継装置と
の間を冷却材である液体金属としての液体ナトリ
ウムを充填して移送する燃料出入機のバツケツト
に関する。
[Detailed Description of the Invention] [Technical Field to which the Invention Pertains] The present invention relates to a fast breeder reactor in which reactor fuel is stored in a container and a fuel inlet/output machine is used to transfer the reactor vessel and reactor in an inert gas atmosphere. The present invention relates to a bucket of a fuel loading/unloading machine that is filled with liquid sodium as a coolant liquid metal and transferred between the bucket and an external fuel relay device.

〔従来技術とその問題点〕 高速増殖炉において原子炉に原子炉燃料(以下
燃料という)としての新燃料を装着したり、使用
済燃料を原子炉から取出して洗浄等の燃料取扱を
行なう燃料取扱設備としてインセルゲリツパシユ
ート方式燃料取扱設備が知られている。第3図は
この燃料取扱設備の構成を示す配置図であり、図
において、1は原子炉容器であり、原子炉容器1
内には冷却材である液体金属としての液体ナトリ
ウムが保有され、液面下に炉心1aおよび炉内燃
料貯蔵ラツク1bが設けられている。燃料交換機
2は原子炉容器1内で燃料交換を行ない、原子炉
容器1からの燃料出し入れ前に炉内貯蔵ラツク1
bに燃料を一時載置して貯蔵する。燃料出入機3
は燃料移送セル20の不活性ガスセル20aに配
設され、原子炉容器1のしやへいプラグを貫通し
て設けられた炉側シユート1cを通つて燃料出入
機3のスイングアーム3aにより燃料を出し入れ
する。そしてスイングアーム3aは不活性ガスセ
ル20a内にてスイング炉外燃料中継装置4の受
け渡し口と接続され、スイングアーム3aと炉外
燃料中継装置4との間で燃料の受け渡しが行なわ
れる。
[Prior art and its problems] Fuel handling involves installing new fuel as reactor fuel (hereinafter referred to as fuel) into the reactor in a fast breeder reactor, and removing spent fuel from the reactor and performing fuel handling such as cleaning. Insert fuel handling equipment is known as such equipment. Figure 3 is a layout diagram showing the configuration of this fuel handling equipment. In the figure, 1 is a reactor vessel;
Liquid sodium as a liquid metal serving as a coolant is stored inside the reactor, and a reactor core 1a and an in-core fuel storage rack 1b are provided below the liquid level. The fuel exchanger 2 exchanges fuel within the reactor vessel 1, and before loading and unloading fuel from the reactor vessel 1, the fuel exchanger 2 exchanges fuel within the reactor vessel 1.
Fuel is temporarily placed and stored in b. Fuel intake/discharge machine 3
is arranged in the inert gas cell 20a of the fuel transfer cell 20, and fuel is taken in and out by the swing arm 3a of the fuel inlet/output machine 3 through the reactor side chute 1c, which is provided by penetrating the damping plug of the reactor vessel 1. do. The swing arm 3a is connected within the inert gas cell 20a to the transfer port of the swing out-of-core fuel relay device 4, and fuel is transferred between the swing arm 3a and the out-of-core fuel relay device 4.

なお、燃料移送セル20は前述の不活性ガスセ
ル20aと湿潤空気セル20bとからなり、不活
性ガスセル20aには炉外燃料中継装置4の他に
破損燃料貯蔵設備6、新燃料地下台車7が、不活
性ガスセル20aと湿潤空気セル20bとにまた
がつて燃料洗浄設備8が、湿潤空気セル20bに
は水中燃料貯蔵槽10、キヤスク台車11がそれ
ぞれの受け渡し口を介して配設されている。ま
た、不活性ガスセル20a、湿潤空気セル20b
にはそれぞれ燃料を移送するインセルグリツパ
5,5aが配設されている。したがつて炉外燃料
中継装置4の中継容器4aに載置された燃料はイ
ンセルグリツ5,5aにより上記の燃料移送セル
20に配された燃料取扱設備間を移送される。な
お天井クレーン12により使用済燃料は搬出トレ
ーラ13に運ばれる。また新燃料は図示しない新
燃料置場より地下台車7により不活性ガスセル2
0aの受け渡し口まで移送される。
The fuel transfer cell 20 is composed of the above-mentioned inert gas cell 20a and humid air cell 20b, and the inert gas cell 20a is equipped with a damaged fuel storage facility 6, a new fuel underground truck 7, in addition to the out-of-core fuel relay device 4. A fuel cleaning facility 8 is disposed astride the inert gas cell 20a and the humid air cell 20b, and an underwater fuel storage tank 10 and a cask truck 11 are disposed in the humid air cell 20b via respective delivery ports. In addition, an inert gas cell 20a, a humid air cell 20b
In-cell grippers 5 and 5a for transferring fuel are respectively disposed. Therefore, the fuel placed in the relay container 4a of the out-of-core fuel relay device 4 is transferred between the fuel handling equipment arranged in the fuel transfer cell 20 by the insel grits 5, 5a. Note that the spent fuel is transported to an unloading trailer 13 by an overhead crane 12. In addition, new fuel is delivered to the inert gas cell 2 by an underground trolley 7 from a new fuel storage area (not shown).
It is transported to the delivery port of 0a.

ところで上記のような燃料取扱に際して燃料出
入機3により原子炉容器1に出し入れされる燃料
は燃料バケツトに収納され、この燃料バケツトが
燃料出入機3のスイングアーム3aに移送され、
スイングアーム3aのスイングにより原子炉容器
1と炉外燃料中継装置4との間で移送される。第
4図は従来の燃料バケツトの断面図であり、図に
おいて不活性ガスセル20aに受け渡し口を介し
て配設された炉外燃料中継装置4の中継容器4a
はフランジ4bによりピツト4cのコンクリート
床に支持されて不活性ガス雰囲気内に据付けられ
ている。燃料15を収納する容器としての燃料バ
ケツト16は燃料出入機のスイングアームが受け
渡し口で接続するガイドレール17に沿つてけん
引具18に接続されており、燃料出入機によるけ
ん引具18の操作により炉外燃料中継装置4の中
継容器4aに出し入れできる。なお第4図は燃料
バケツト16が中継容器4aに収納された状態を
示している。燃料バケツト16には側壁にサイフ
オン管16aを設けており、燃料バケツト16に
充填した液体ナトリウムの30の液面30aはサ
イフオン管16aの内壁の開口位置に定められて
いる。燃料15は図示しない燃料出入機のグリツ
パ19の複数の爪19aを開にして、燃料15の
グリツプ部15aに挿入して把持され、液体ナト
リウム30中に浸漬されている。
By the way, when handling fuel as described above, the fuel taken in and out of the reactor vessel 1 by the fuel inlet/outlet machine 3 is stored in a fuel bucket, and this fuel bucket is transferred to the swing arm 3a of the fuel inlet/outlet machine 3.
The fuel is transferred between the reactor vessel 1 and the extra-core fuel relay device 4 by swinging the swing arm 3a. FIG. 4 is a sectional view of a conventional fuel bucket, and in the figure, a relay container 4a of an out-of-core fuel relay device 4 is installed through a delivery port to an inert gas cell 20a.
is supported by a flange 4b on the concrete floor of a pit 4c and installed in an inert gas atmosphere. A fuel bucket 16 serving as a container for storing fuel 15 is connected to a traction tool 18 along a guide rail 17 to which the swing arm of the fuel loading/unloading machine connects at the delivery port, and the fuel bucket 16 is connected to a traction tool 18 by operating the traction tool 18 by the fuel loading/unloading machine. It can be taken in and out of the relay container 4a of the external fuel relay device 4. Note that FIG. 4 shows a state in which the fuel bucket 16 is housed in the relay container 4a. The fuel bucket 16 is provided with a siphon pipe 16a on its side wall, and the liquid level 30a of liquid sodium filled in the fuel bucket 16 is set at the opening position of the inner wall of the siphon pipe 16a. The fuel 15 is held by opening a plurality of claws 19a of a gripper 19 of a fuel inlet/output machine (not shown), inserted into a grip portion 15a of the fuel 15, and immersed in liquid sodium 30.

燃料バケツト16内の液体ナトリウムは原子炉
容器内の冷却材としての液体ナトリウムが充填さ
れたものであり、燃料出入機により原子炉容器の
液体ナトリウム液面上に吊り上げられたとき燃料
バケツト16の上端面まで満たされた液体ナトリ
ウムがサイフオン管16aから原子炉容器内に流
出して液面30aが保持されている。なおこの液
面30aは燃料15を充分カバーする高さとして
いる。このため燃料、特に使用済燃料を燃料バケ
ツト16により移送する際、崩壊熱は燃料15の
複数のエントランスノズル孔15bと燃料15内
の燃料ピン間の冷却材通流チヤンネルと頂部の開
口15cとを介して矢印方向の液体ナトリウムの
自然循環により除去され、特に移送中に事故が生
じ長時間同一場所に停留してもこの自然循環によ
つて崩壊熱は除去される。ところで燃料バケツト
16内の燃料15は液体ナトリウム中にあるの
で、インセルグリツパのグリツパ19の爪19a
を開閉するつかみ機構の爪操作部は液体ナトリウ
ム中で作動が行なわれて燃料15を把持、釈放し
ている。
The liquid sodium in the fuel bucket 16 is filled with liquid sodium as a coolant in the reactor vessel, and when it is lifted above the liquid sodium level in the reactor vessel by the fuel loading/unloading machine, it is suspended above the fuel bucket 16. Liquid sodium filled to the end surface flows out from the siphon tube 16a into the reactor vessel, and a liquid level 30a is maintained. Note that this liquid level 30a is set to a height that sufficiently covers the fuel 15. Therefore, when fuel, especially spent fuel, is transferred by the fuel bucket 16, decay heat flows through the coolant flow channels between the plurality of entrance nozzle holes 15b of the fuel 15, the fuel pins in the fuel 15, and the opening 15c at the top. The decay heat is removed by the natural circulation of the liquid sodium in the direction of the arrow through the sodium chloride, and even if an accident occurs during transportation and the sodium stays in the same place for a long time, the decay heat is removed by this natural circulation. By the way, since the fuel 15 in the fuel bucket 16 is in liquid sodium, the claws 19a of the gripper 19 of the incel gripper
The claw operating portion of the gripping mechanism that opens and closes the fuel 15 is operated in liquid sodium to grip and release the fuel 15.

しかしながら、このような構造ではグリツパ1
9a等からなる爪操作部、例えば爪を開閉する回
動部等には液体ナトリウムが付着し、この状態で
液体ナトリウム外に取出されて冷却されるとつか
み機構の爪操作部等がナトリウムにより固着して
燃料を把持、釈放する操作ができなくなるという
問題がある。このため固着したナトリウムを加熱
して溶け流す加熱装置や、頻繁にグリツパのつか
み機構を洗浄することが必要となり、このため設
備費がかゝり、また燃料交換時間が長くなるとい
う問題がある。
However, in such a structure, the gripper 1
Liquid sodium adheres to the claw operating parts such as 9a, for example, the rotating parts that open and close the claws, and when the liquid sodium is taken out of the liquid sodium in this state and cooled, the claw operating parts of the gripping mechanism, etc. become stuck with the sodium. There is a problem in that it becomes impossible to hold and release the fuel. For this reason, it is necessary to use a heating device to heat and melt the fixed sodium and to frequently clean the grasping mechanism of the gripper, which raises the problem of increased equipment costs and longer refueling time.

〔発明の目的〕[Purpose of the invention]

本発明は、前述のような点に鑑みインセルグリ
ツパのグリツパのつかみ機構を固着の原因となる
液体金属内への浸漬を行なわずに燃料バケツト内
の燃料を把持、釈放して燃料を移送できる燃料出
入機の燃料バケツトを提供することを目的とす
る。
In view of the above-mentioned points, the present invention provides a fuel inlet/output system that can grip and release fuel in a fuel bucket to transfer fuel without immersing the gripping mechanism of an in-cell gripper in liquid metal that may cause sticking. The purpose is to provide fuel buckets for aircraft.

〔発明の要旨〕[Summary of the invention]

上記の目的は、本発明によれば原子炉燃料を収
納する容器の側壁に備えたサイフオンは、原子炉
燃料のグリツプ部が使用済燃料の崩壊熱に伴う液
体金属の熱膨張により上昇して定まる液体金属液
面より上に露出するように容器の内面に開口を有
し、かつ該サイフオン管の有効高さは燃料移送時
に燃料出入機内に傾斜させたまゝ燃料を収納した
容器を停止させたとき液体金属の熱膨張により上
昇する液体金属液面を保持するようにしたことに
よつて達成される。
According to the present invention, the siphon provided on the side wall of the container housing the reactor fuel is fixed by the grip of the reactor fuel rising due to the thermal expansion of the liquid metal accompanying the decay heat of the spent fuel. The container has an opening on its inner surface exposed above the liquid metal surface, and the effective height of the siphon tube is such that the effective height of the siphon tube remains tilted within the fuel inlet/output device during fuel transfer and when the container containing fuel is stopped. This is achieved by maintaining the liquid metal level which rises due to thermal expansion of the liquid metal.

〔発明の実施例〕[Embodiments of the invention]

以下図面に基づいて本発明の実施例を説明す
る。第1図は本発明の実施例による燃料出入機の
燃料バケツトを炉外燃料中継装置に収納した部分
断面図である。なお第1図および後述する第2図
において第3図、第4図の従来例と同一部品には
同じ符号を付している。第1図において炉外燃料
中継装置4、中継容器4a、燃料15、燃料バケ
ツト16、けん引具18、グリツパ19等の構
造、作用は従来技術と同じなので説明を省略す
る。本実施例では燃料バケツト16の側壁に設け
られるサイフオン管16aの内壁開口で定まる冷
却材である液体金属としての液体ナトリウムの液
面Aは炉外燃料中継装置4から下流の燃料取扱装
置に移送されるまでの約30分程度の短時間の間に
収納された燃料15、特に使用済燃料の崩壊熱に
より液体ナトリウムが熱膨脹して液面Bまで上昇
するが、燃料15のグリツプ部15aが液面B上
の空間に露出するようにサイフオン管16aの位
置を定めている。なおサイフオン管16aの有効
高さはこの収納時における熱膨脹による液面上昇
より高くなる後述する移送中継時の液面上昇、す
なわち傾斜したガイドレール17に沿つて傾斜し
た燃料バケツトの液体ナトリウムの液面が熱膨脹
により上昇しても、充填された液体ナトリウムが
サイフオン管内を通つて燃料バケツト外に排出さ
れないようにとられている。
Embodiments of the present invention will be described below based on the drawings. FIG. 1 is a partial cross-sectional view of a fuel bucket of a fuel inlet/outlet device according to an embodiment of the present invention, which is housed in an out-of-core fuel relay device. In FIG. 1 and FIG. 2, which will be described later, the same parts as in the conventional example shown in FIGS. 3 and 4 are given the same reference numerals. In FIG. 1, the structures and functions of the out-of-core fuel relay device 4, relay container 4a, fuel 15, fuel bucket 16, traction tool 18, gripper 19, etc. are the same as those in the prior art, so their explanations will be omitted. In this embodiment, the liquid level A of liquid sodium as a liquid metal, which is a coolant, determined by the inner wall opening of the siphon pipe 16a provided on the side wall of the fuel bucket 16 is transferred from the out-of-core fuel relay device 4 to the downstream fuel handling device. During a short period of about 30 minutes until the fuel 15 is stored, the liquid sodium thermally expands due to the decay heat of the spent fuel and rises to the liquid level B, but the grip part 15a of the fuel 15 does not reach the liquid level. The siphon tube 16a is positioned so as to be exposed to the space above B. Note that the effective height of the siphon tube 16a is higher than the liquid level rise due to thermal expansion during storage, which will be described later. Even if the liquid sodium rises due to thermal expansion, the liquid sodium filled in the siphon tube is prevented from being discharged to the outside of the fuel bucket through the inside of the siphon tube.

このような構造により炉外燃料中継装置4の中
継容器4aに収納された燃料15はそグリツプ部
15aが熱膨脹により上昇した液体ナトリウム液
面B上の空間にあるのでグリツパ19のつかみ機
構は液面B上の空間、すなわちグリツパ19の爪
の開閉は液面上の不活性ガス雰囲気中で行なわれ
る。このためグリツパ19のつかみ機構の爪操作
部等は液体ナトリウム中に浸されないのでナトリ
ウムが爪操作部の爪開閉回動部に付着しないため
冷却による固着が発生せず、良好な爪開閉能力を
長時間にわたつて保持できる。
With this structure, the grip portion 15a of the fuel 15 stored in the relay container 4a of the out-of-core fuel relay device 4 is located in a space above the liquid sodium level B that has risen due to thermal expansion, so the gripping mechanism of the gripper 19 is The opening and closing of the space above B, that is, the claws of the gripper 19, is performed in an inert gas atmosphere above the liquid level. For this reason, the claw operation part of the gripper 19's gripping mechanism is not immersed in liquid sodium, so sodium does not adhere to the claw opening/closing rotating part of the gripper 19, so sticking due to cooling does not occur, and good claw opening/closing ability is maintained. Can be retained over time.

なお、通常の燃料移送の場合燃料15は前述の
ように燃料バケツト16内に短時間だけ留まるの
で燃料15が使用済燃料であつてもその崩壊熱に
より燃料の温度を異常上昇させない。
In addition, in the case of normal fuel transfer, the fuel 15 remains in the fuel bucket 16 for only a short time as described above, so even if the fuel 15 is a spent fuel, its decay heat will not cause the temperature of the fuel to rise abnormally.

第2図は第3図の燃料バケツト使用済燃料を収
納した状態で炉外燃料中継装置と原子炉容器との
間を傾斜したシユートスリーブ22に沿つて燃料
出入機のけん引具18により移送中、事故により
移送が中継されて停止した燃料バケツト16の状
態を示している。この場合ナトリウム液面は当初
サイフオン管16aで定まる液面cにあるが、グ
リツプ部15aは不活性ガス中にあるので燃料バ
ケツト内で自然循環が行なわれないため液体ナト
リウムは温度上昇し液面は上昇する。そして長時
間の停止により液面がD液面まで上昇すると燃料
15はナトリウム液面D以下に浸漬される。この
ため燃料15のエントラインスノズル孔15bと
頂部の開口15cとを介して矢印方向に前述のよ
うに自然循環が行なられ、使用済燃料の崩壊熱を
除去して使用済燃料の温度の異常上昇を生じさせ
ず、またナトリウム液面も液面Dを保持する。ま
た、サイフオン管16aの有効高さは前述のよう
に液面Dに上昇しても燃料バケツト16内のナト
リウム液がサイフオン管16aを通つて外部にこ
ぼれない高さとしているのでナトリウム液面は保
持される。
Figure 2 shows the spent fuel in the fuel bucket shown in Figure 3 being transported between the external fuel relay device and the reactor vessel along the inclined shute sleeve 22 by the towing tool 18 of the fuel inlet/outlet machine. , shows the state of the fuel bucket 16 whose transfer was relayed and stopped due to an accident. In this case, the sodium liquid level is initially at the liquid level c determined by the siphon tube 16a, but since the grip portion 15a is in an inert gas, natural circulation does not take place within the fuel bucket, the temperature of the liquid sodium rises, and the liquid level increases. Rise. When the liquid level rises to the liquid level D due to a long stop, the fuel 15 is immersed below the sodium liquid level D. Therefore, the natural circulation of the fuel 15 is performed in the direction of the arrow as described above through the entrance nozzle hole 15b and the opening 15c at the top, and the decay heat of the spent fuel is removed and the temperature of the spent fuel is abnormal. No rise occurs, and the sodium liquid level also maintains the liquid level D. In addition, the effective height of the siphon tube 16a is set to such a height that even if the liquid level rises to D, the sodium liquid in the fuel bucket 16 does not spill out through the siphon tube 16a, so the sodium liquid level is maintained. be done.

なお事故が回復し、正常状態になつた時は再び
燃料バケツトを燃料出入機により原子炉容器内の
液体ナトリウムに浸漬して冷却後再びナトリウム
液面上の不活性ガスのカバーガス中に引き上げる
ことにより、燃料バケツト16内の液面はサイフ
オン管16aの内壁の開口位置で定まる液面A
(第1図参照)を保持する。したがつて燃料バケ
ツトに収納された燃料は再び液体ナトリウムにグ
リツパのつかみ機構を浸漬せずにグリツパにより
把持、釈放される。
When the accident recovers and normal conditions return, the fuel bucket should be immersed in the liquid sodium inside the reactor vessel again using the fuel inlet/output machine, cooled, and then raised again into the inert gas cover gas above the sodium liquid level. Therefore, the liquid level in the fuel bucket 16 is the liquid level A determined by the opening position of the inner wall of the siphon pipe 16a.
(See Figure 1). Therefore, the fuel stored in the fuel bucket is gripped and released by the gripper without immersing the gripper's gripping mechanism in liquid sodium again.

〔発明の効果〕〔Effect of the invention〕

以上の説明から明らかなように、本発明によれ
ば原子炉燃料を収納する燃料バケツトの液体金属
液面を、燃料バケツトの側壁に設けられたサイフ
オン管により定め、さらに燃料バケツトの通常移
送時に使用済燃料としての原子炉燃料の崩壊熱に
より前記液面より上昇した液面から露出して原子
燃料のグリツプ部を位置させ、かつサイフオン管
の有効高さを燃料バケツトが傾斜したシユートス
リーブ上で事故により停止した場合液体金属液面
が熱膨脹により上昇しても液面を保持し得るもの
としたことにより、燃料を把持、釈放するグリツ
パは常にナトリウム液面より上の不活性ガス中で
行なわれるので、ナトリウムがグリツパのつかみ
機構に付着して爪の開閉等の操作部が固着しない
ので、固着を溶かす加熱装置を必要としないため
設備費が安くなり、またグリツパのつかみ機構の
洗浄頻度も低減して燃料取扱時間も短縮できる。
また移送事故時、燃料バケツトが停止しても使用
済燃料の崩壊熱を液体金属の熱膨脹による液体金
属液面の上昇により使用済燃料を液体金属が覆う
ことになるので自然循環が行なわれ、崩壊熱の除
去を良好に行ない、燃料の溶融を防止できるとい
う効果がある。
As is clear from the above description, according to the present invention, the liquid metal level of the fuel bucket containing reactor fuel is determined by the siphon pipe provided on the side wall of the fuel bucket, and is further used during normal transfer of the fuel bucket. The grip part of the nuclear fuel is positioned so as to be exposed above the liquid level which has risen above the liquid level due to the decay heat of the reactor fuel, and the effective height of the siphon tube is adjusted so that the fuel bucket is on the inclined shoot sleeve. In the event of a shutdown due to an accident, the liquid metal level can be maintained even if it rises due to thermal expansion, so the gripper that grips and releases the fuel is always operated in an inert gas above the sodium liquid level. This prevents sodium from adhering to the gripper's gripping mechanism and causing it to stick to the operating parts for opening and closing the claws.Therefore, there is no need for a heating device to melt the adhesion, reducing equipment costs and reducing the frequency of cleaning the gripper's gripping mechanism. The fuel handling time can also be shortened.
In addition, in the event of a transfer accident, even if the fuel bucket stops, the spent fuel's decay heat is absorbed by the thermal expansion of the liquid metal, which causes the liquid metal level to rise and the spent fuel to be covered by the liquid metal, allowing for natural circulation and collapse. This has the effect of effectively removing heat and preventing melting of the fuel.

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

第1図は本発明の実施例による燃料出入機の燃
料バケツトを炉外燃料中継装置に収納した部分断
面図、第2図は第1図の燃料バケツトをシユート
スリーブに沿う移送時に停止した状態を示す部分
断面図、第3図は燃料取扱設備の配置図、第4図
は従来の燃料出入機の燃料バケツトを炉外燃料中
継装置に収納した部分断面図である。 1:原子炉容器、3:燃料出入機、4:炉外燃
料中継装置、5:インセルグリツパ、15:原子
炉燃料、15a:グリツプ部、16:燃料バケツ
ト、16a:サイフオン管、19:グリツパ。
Fig. 1 is a partial sectional view of a fuel bucket of a fuel inlet/outlet machine according to an embodiment of the present invention housed in an extra-core fuel relay device, and Fig. 2 shows a state in which the fuel bucket of Fig. 1 is stopped during transfer along a chute sleeve. 3 is a layout diagram of fuel handling equipment, and FIG. 4 is a partial sectional view showing a fuel bucket of a conventional fuel inlet/output machine housed in an extra-core fuel relay device. 1: Reactor vessel, 3: Fuel inlet/output machine, 4: External fuel relay device, 5: Incel gripper, 15: Reactor fuel, 15a: Grip section, 16: Fuel bucket, 16a: Siphon tube, 19: Gripper.

Claims (1)

【特許請求の範囲】[Claims] 1 不活性ガス雰囲気にて冷却材として液体金属
を充填し、側壁にサイフオンを備え、原子炉燃料
を収納する容器からなり、頂部にグリツプ部を有
する原子炉燃料を原子炉容器から出入する燃料出
入機の燃料バケツトにおいて、前記サイフオン
は、前記原子炉燃料のグリツプ部が使用済燃料の
崩壊熱に伴う液体金属の熱膨脹により上昇して定
まる液体金属液面より上に露出するように容器の
内面に開口を有し、かつ該サイフオン管の有効高
さは燃料移送時に燃料出入機内に傾斜させたまゝ
燃料を収納した容器を停止させたとき、液体金属
の熱膨脹により上昇する液体金属液面を保持する
ようにしたことを特徴とする燃料出入機の燃料バ
ケツト。
1. A container that is filled with liquid metal as a coolant in an inert gas atmosphere, equipped with a siphon on the side wall, and that stores the reactor fuel, and has a grip on the top. In a fuel bucket for a nuclear power plant, the siphon is attached to the inner surface of the container so that the grip of the reactor fuel is exposed above the liquid metal level determined by rising due to the thermal expansion of the liquid metal due to the decay heat of the spent fuel. The siphon tube has an opening, and the effective height of the siphon tube is such that it maintains the liquid metal level that rises due to thermal expansion of the liquid metal when the container containing the fuel is stopped while remaining inclined in the fuel inlet/output machine during fuel transfer. A fuel bucket for a fuel inlet/output machine characterized by the following features.
JP60120872A 1985-06-04 1985-06-04 Fuel packet for fuel unloader/loader Granted JPS61278796A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60120872A JPS61278796A (en) 1985-06-04 1985-06-04 Fuel packet for fuel unloader/loader

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60120872A JPS61278796A (en) 1985-06-04 1985-06-04 Fuel packet for fuel unloader/loader

Publications (2)

Publication Number Publication Date
JPS61278796A JPS61278796A (en) 1986-12-09
JPH0334836B2 true JPH0334836B2 (en) 1991-05-24

Family

ID=14797036

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60120872A Granted JPS61278796A (en) 1985-06-04 1985-06-04 Fuel packet for fuel unloader/loader

Country Status (1)

Country Link
JP (1) JPS61278796A (en)

Also Published As

Publication number Publication date
JPS61278796A (en) 1986-12-09

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