JPS63315994A - Continuous dissolving treatment device for spent nuclear fuel - Google Patents

Continuous dissolving treatment device for spent nuclear fuel

Info

Publication number
JPS63315994A
JPS63315994A JP62151221A JP15122187A JPS63315994A JP S63315994 A JPS63315994 A JP S63315994A JP 62151221 A JP62151221 A JP 62151221A JP 15122187 A JP15122187 A JP 15122187A JP S63315994 A JPS63315994 A JP S63315994A
Authority
JP
Japan
Prior art keywords
fuel
fuel loading
loading basket
cladding
basket
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
JP62151221A
Other languages
Japanese (ja)
Other versions
JPH0658430B2 (en
Inventor
Yoshie Sasaki
淑江 佐々木
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP15122187A priority Critical patent/JPH0658430B2/en
Publication of JPS63315994A publication Critical patent/JPS63315994A/en
Publication of JPH0658430B2 publication Critical patent/JPH0658430B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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
    • 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
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

Abstract

PURPOSE:To exactly take cladding pipes out of a fuel loading cage in a limited space by constituting a loading cage gripper of a fuel loading cage lifting device in such a manner that the loading cage is automatically turned down at the time of lifting the loading cage. CONSTITUTION:A cladding pipe taking-out section 9 is provided to the upper part of a circular dissolving vessel 1 which consists of a dissolution treating liquid 3, a feed port 29 and a discharge port 30 and is disposed with the plural fuel loading cages in the circumferential direction thereof. A cover 8 is provided to the upper part of this dissolving vessel 1 and the cladding pipe taking-out section 9 to maintain airtightness. A cladding pip taking-out port 4 is provided to part thereof. The fuel loading cage gripper 5 is coupled to the lifting device 6 and the lower part of the loading cage 2 is freely turnably gripped by the gripper 5. The loading cage 2 is turned down into the cladding pipe taking-out port 4 by a guide plate 7 and its own weight of the cage 2 when the gripped cage 2 is hoisted. The cladding pipes in the cage 2 is thus surely taken out.

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、使用済原子燃料の再処理工程において使用済
原子燃料を加熱された硝酸で溶解し、不溶解性の被覆管
と分離する装置、特に、核分裂性物質の濃度の高い原子
燃料を連続的に高能率で溶解処理するために、燃料装荷
かとからの被覆管の取出しを的確に行うのに好適な装置
に関する。
Detailed Description of the Invention [Industrial Application Field] The present invention provides an apparatus for dissolving spent nuclear fuel with heated nitric acid and separating it from insoluble cladding in a spent nuclear fuel reprocessing process. In particular, the present invention relates to an apparatus suitable for accurately removing a cladding tube from a fuel loading tank in order to continuously and efficiently melt nuclear fuel with a high concentration of fissile material.

〔従来の技術〕[Conventional technology]

原子炉内における核分裂反応によりエネルギーを放出し
、核分裂性物質を消費して使用に適さなくなった原子燃
料は、一般に使用済原子燃料と呼ばれる。この使用済原
子燃料に含まれている核分裂性物質や原子燃料物質を回
収し、再利用するための工程が再処理である。
Nuclear fuel that releases energy through a nuclear fission reaction in a nuclear reactor and consumes fissile material and is no longer suitable for use is generally referred to as spent nuclear fuel. Reprocessing is the process of recovering and reusing the fissile material and nuclear fuel material contained in this spent nuclear fuel.

再処理の工程は更に多岐にわたる単位工程から成ってい
る。ピコレックス法においては、その最初の段階で、燃
料棒は小片に剪断され、続いて中味の原子燃料物質が硝
酸に溶解される。この燃料片の被覆管は、一般にジルコ
ニウム合金あるいはステンレス鋼なので硝酸には溶解せ
ず、原子燃料物質が溶解し終えた後に分別可能となる。
The reprocessing process further consists of a wide variety of unit processes. In the Picolex process, in the first step, the fuel rods are sheared into small pieces and the nuclear fuel material inside is subsequently dissolved in nitric acid. The cladding tube of this fuel piece is generally made of zirconium alloy or stainless steel, so it does not dissolve in nitric acid and can be separated after the nuclear fuel material is completely dissolved.

ところで、使用済原子燃料の溶解を行う装置としては、
原子燃料を装荷した耐食性容器中に必要量の硝酸を加え
て燃料溶解を完了させた後溶解処理液を取り出すいわゆ
る回分方式と、容器に原子燃料と硝酸を装荷しながら溶
解処理液を取り出す連続方式、並びに両者の折衷的な性
格を有する半連続方式がある。一般に連続式は回分式に
比べ高能率ではあるが、被覆管等不溶解物の取り出しに
問題があり、その解決案として特開昭56−94297
号公報記載の処理物を連続的に処理する装置が提供され
た。この装置は、同格で支持した燃料装荷かごを縦方向
に回転移動させ、回転の中心より上に位置する燃料装荷
かとから被覆管を重力により落下させて投棄するもので
あった。
By the way, as a device for melting spent nuclear fuel,
There is a so-called batch method in which the necessary amount of nitric acid is added into a corrosion-resistant container loaded with nuclear fuel to complete fuel dissolution and then the dissolution treatment liquid is taken out, and a continuous method in which the dissolution treatment liquid is taken out while loading nuclear fuel and nitric acid into the container. , as well as semi-continuous systems that have a compromise between the two. In general, the continuous type is more efficient than the batch type, but there is a problem in removing undissolved materials such as cladding tubes.
An apparatus for continuously processing the processed material described in the above publication was provided. This device rotated the fuel loading baskets, which were supported on the same level, in the vertical direction, and dropped the cladding tubes by gravity from the fuel loading basket located above the center of rotation, and dumped them.

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

しかし、この装置は縦長構造であるために耐震性の点で
不利であること、また、構造が複雑であるために被覆管
による経路的目詰りを起すという懸念がある。被覆管に
よる目詰りを回避するために水平に保持した溶解槽中の
溶解処理液に燃料片を装荷した容器を浸漬し、溶解の終
了した容器から被覆管を取り出すことを特徴とする連続
溶解処理装置の研究開発が進められている。例えば特開
昭61−99893号公報記載の直配列式連続溶解装置
は、直線上に配置した複数の溶解容器内にコンベアで燃
料剪断片を供給する方式の連続溶解処理装置である。こ
の公知例に代表され・るように、溶解容器内の被覆管の
取出しを、何らかの駆動機構を備えた装置を用いて的確
に行う必要がある。
However, since this device has a vertically elongated structure, it is disadvantageous in terms of earthquake resistance, and since the structure is complex, there is a concern that clogging of the path by the cladding tube may occur. A continuous melting process characterized by immersing a container loaded with fuel pieces in a melting solution in a melting tank held horizontally to avoid clogging of the cladding tube, and then removing the cladding tube from the container after melting. Research and development of the device is underway. For example, a straight-array continuous melting apparatus described in Japanese Patent Application Laid-Open No. 61-99893 is a continuous melting processing apparatus in which fuel sheared pieces are fed by a conveyor into a plurality of melting containers arranged in a straight line. As typified by this known example, it is necessary to accurately take out the cladding tube from the melting container using a device equipped with some kind of drive mechanism.

しかし、溶解処理装置は高濃度の放射性物質及び高温・
高濃度の酸を取り扱うため、駆動部は定期的な保守が必
要であるが、その保守は、放射能の高い雰囲気下で行わ
れるため、非常に困難となる。従って、保守の容易性と
ともに、保守頻度の少ない、すなわち簡略で駆動部の少
ない機構が望まれている。また、被覆管の取出しに当た
って、放射性物質が装置外に出て汚染が拡大される恐れ
があり、コンパクトな形状で装置の気密性を保持できる
ような機構が望まれている。
However, the dissolution treatment equipment handles high concentrations of radioactive materials and high temperatures.
Since the drive unit handles highly concentrated acids, regular maintenance is required, but this maintenance is extremely difficult because it is performed in an atmosphere with high radioactivity. Therefore, there is a desire for a mechanism that is easy to maintain and requires less frequent maintenance, that is, a mechanism that is simple and has fewer driving parts. Furthermore, when taking out the cladding tube, there is a risk that radioactive substances may come out of the device and spread contamination, so a mechanism that is compact and can maintain airtightness of the device is desired.

本発明の目的は、保守頻度の少なく、かつ保守が容易で
あり、被覆管の取出しに際して汚染拡大のないように気
密性を保持し易いコンパクトな形状で、被覆管の取出し
を的確に行いうる機構を有する連続溶解処理装置を提供
するとにある。
It is an object of the present invention to provide a mechanism that requires less maintenance, is easy to maintain, has a compact shape that is easy to maintain airtightness to prevent the spread of contamination when removing the cladding, and is capable of accurately removing the cladding. The purpose of the present invention is to provide a continuous melting treatment apparatus having the following features.

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

上記目的は、(a)溶解処理液を充填し、かつ使用済原
子燃料を溶解するための円形状の溶解槽、(b)使用済
原子燃料を装荷し、かつ前記溶解槽内に浸漬するための
ものであって該溶解槽内に並べて配置された複数個の燃
料装荷かと、(c)該燃料装荷かごを溶解槽から出し入
れするための燃料装荷かご把持装置を備えた燃料装荷か
ご昇降装置、(d)不溶解燃料被覆管の取出口、(e)
溶解処理液の供給口及び(f)排出口を含む使用済原子
燃料の連続溶解処理装置において、前記燃料装荷かご昇
降装置に備えられた燃料装荷かご把持装置は、使用済原
子燃料溶解処理終了後における不溶解燃料被覆管を含む
燃料装荷かご全体の重心位置よりも下部の位置において
回動自在に把持するように構成することにより該燃料装
荷かごを上昇させたとき該燃料装荷かごが自動的に転倒
し、上部の開口部が下向きになるようにして内部の不溶
解燃料被覆管を前記不溶解燃料被覆管の取出口に排出で
きるように構成することにより達成される。
The above purposes are (a) a circular dissolution tank filled with a dissolution treatment liquid and for dissolving the spent nuclear fuel; (b) for loading spent nuclear fuel and immersing it in the dissolution tank; (c) a fuel loading basket lifting device equipped with a fuel loading basket gripping device for taking the fuel loading basket in and out of the melting tank; (d) Undissolved fuel cladding outlet, (e)
In a continuous spent nuclear fuel dissolution processing device that includes a dissolution treatment liquid supply port and (f) a discharge port, a fuel loading basket gripping device provided in the fuel loading basket lifting device is configured to dispose of the spent nuclear fuel after the spent nuclear fuel dissolution processing is completed. When the fuel loading basket is raised, the fuel loading basket is automatically moved This is achieved by inverting the tube so that the upper opening faces downward so that the internal undissolved fuel cladding tube can be discharged to the outlet of the undissolved fuel cladding tube.

本発明によれば、燃料装荷かとは中に被覆管が入ってお
り、燃料装荷かごを把持した部分、すなわち1把持点よ
りも重心が高い位置にあり、燃料装荷かごが自身にかか
る重力によって傾くことになる。この際、把持部は、把
持点を中心にして燃料装荷かごが回動自在となる機構と
する。また、必ず、被覆管取出[]の存在する側に燃料
装荷かごが傾くようにするために、被覆管取出口の反対
側に傾いた際に燃料装荷かごを押し戻す手段、または、
押圧する構造を有したガイド板を設置する。
According to the present invention, the fuel loading basket has a cladding tube inside, and the center of gravity is located higher than the part where the fuel loading basket is gripped, that is, the one gripping point, and the fuel loading basket is tilted by the gravity applied to itself. It turns out. At this time, the gripping portion has a mechanism that allows the fuel loading basket to rotate freely around the gripping point. In addition, in order to ensure that the fuel loading basket is always tilted to the side where the cladding tube extraction port exists, a means for pushing back the fuel loading basket when the fuel loading basket is tilted to the opposite side of the cladding tube extraction port, or
A guide plate with a pressing structure is installed.

〔作用〕[Effect]

本発明の装置によれば、溶解処理終了後、溶解槽内から
燃料装荷かごを吊り上げたとき、該燃料装荷かとは、該
かご自体及び不溶解燃料被覆管の重量を考慮して設計し
ており、その重心位置が把持点よりも高くなるよう構成
しであるため、該把持点を中心に回動して傾き、前記燃
料装荷かごの上部の開口部が下向きになる。従って、吊
り上げた位置の上部に被覆管取出口を配置しておけば、
傾いた燃料装荷かとは上部の開口部からその被覆管取出
口へ倒れ込み、更に燃料装荷かごを上方へ吊り上げるこ
とにより、燃料装荷かとは被覆管取出口内に転倒し、中
の被覆管を放出し、これを取出すことができる。このよ
うに、吊り上げの駆動部と1把持の駆動部という簡mか
つ少ない駆動部で被覆管の的確な取出しが可能になる。
According to the device of the present invention, when the fuel-loaded basket is lifted from the melting tank after the melting process is completed, the weight of the fuel-loaded basket is designed in consideration of the weight of the basket itself and the undissolved fuel cladding tube. Since the center of gravity is configured to be higher than the gripping point, the fuel basket rotates and tilts around the gripping point, so that the opening at the top of the fuel loading basket faces downward. Therefore, if the cladding pipe outlet is placed at the top of the lifted position,
A tilted fuel container falls into its cladding tube outlet through the opening at the top, and by lifting the fuel loading basket upward, the fuel loaded container falls into the cladding tube outlet, releasing the cladding tube inside. , this can be retrieved. In this way, the cladding tube can be taken out accurately with a simple and small number of drive parts, ie, a lifting drive part and one gripping drive part.

〔実施例〕〔Example〕

以下、本発明の詳細な説明する。 The present invention will be explained in detail below.

第1図は本発明の一実施例になる連続溶解処理装置の垂
直方向の断面図である。第1図において円形状の溶解槽
1の中には、高温・高酸1度の溶解処理液3が入ってお
り、複数個の燃料装荷かと2が円周方向に配置され、燃
料装荷かと2の下部が溶解処理液3に浸漬している。燃
料装荷かと2には燃料剪断片が装荷されており、これが
溶解処理液3の中で燃料のみ溶解し、不溶解性の燃料の
被覆管が燃料装荷かと2に残存するようになっている。
FIG. 1 is a vertical sectional view of a continuous melting treatment apparatus according to an embodiment of the present invention. In FIG. 1, a circular melting tank 1 contains a high temperature, highly acidic, 1 degree melting treatment liquid 3, and a plurality of fuel loading containers 2 are arranged in the circumferential direction. The lower part of is immersed in the dissolving treatment liquid 3. The fuel loading shell 2 is loaded with fuel shear pieces, and only the fuel is dissolved in the dissolution treatment liquid 3, so that an insoluble fuel cladding tube remains in the fuel loading shell 2.

溶解槽1の上部は、カバー8により気密性が保持されて
いる。溶解処理液3は、供給口29より溶解槽1内に供
給され、排出口30より排出される。燃料装荷かご把持
装置5は、燃料装荷かご昇降′!A置6に吊り下げられ
た状態で結合され、燃料装荷かご昇降装置6はカバー8
により保持され、燃料装荷かご把持装置5がカバー8の
内側にくるように設置される。
The upper part of the dissolution tank 1 is kept airtight by a cover 8. The dissolution treatment liquid 3 is supplied into the dissolution tank 1 from the supply port 29 and discharged from the discharge port 30. The fuel loading basket gripping device 5 lifts and lowers the fuel loading basket'! The fuel loading car lifting device 6 is attached to the cover 8 in a suspended state.
The fuel loading basket gripping device 5 is installed so as to be placed inside the cover 8.

すなわち、被覆管取出部9はカバー8により覆われ、溶
解処理装置全体の気密性が保持できる。被覆管取出口4
は、被覆管取出部9と接続している。燃料装荷かご2の
中の被覆管を取出すために、まず、燃料装荷かご把持装
置5が燃料装荷かご2をつかみ、燃料装荷かご昇降装置
6により吊り上げ、燃料装荷かご2が白身にかかる重力
により被覆管取出口4内へ倒れ込み、中の被覆管が取出
される。被覆管取出口4と反対側へ倒れた場合は、ガイ
ド板7により燃料装荷かと2を押し戻し、常に被覆管取
出口4内へ倒れ込むようになっている。
That is, the cladding tube removal section 9 is covered with the cover 8, and the airtightness of the entire melting treatment apparatus can be maintained. Cladding tube outlet 4
is connected to the cladding tube removal section 9. In order to take out the cladding tube inside the fuel loading basket 2, the fuel loading basket gripping device 5 first grasps the fuel loading basket 2, lifts it up with the fuel loading basket lifting device 6, and the fuel loading basket 2 is coated by the gravity applied to the white. It falls into the tube outlet 4 and the cladding tube inside is taken out. If it falls to the side opposite to the cladding tube outlet 4, the guide plate 7 pushes back the fuel loading port 2 so that it always falls into the cladding tube outlet 4.

次に、第2図により、燃料被覆管の取出し方法を詳細に
説明する。第2図(、)は、燃料装荷かと2を把持する
位置における動作を示す断面図である。
Next, the method for removing the fuel cladding tube will be explained in detail with reference to FIG. FIG. 2(,) is a sectional view showing the operation at a position where the fuel loading lever 2 is gripped.

燃料装荷かご昇降装置6が下降し、溶解槽1内に配置さ
れている燃料装荷かと2の重心位置より底部に近い位置
を燃料装荷かご把持装置5により把持する。次に、燃料
装荷かご昇降装置6が燃料装荷かと2を吊り上げ、被覆
管取出部9へ運ぶ。第2図(b)は、被覆管取出口4へ
燃料装荷かと2が倒れ込む動作を示す断面図である。燃
料装荷かご把持装置5の把持部10は、燃料装荷かと2
が回?自在となるような機構になっているので、燃料装
荷かと2のバランスにより、矢印へのように重心位置1
1が移動する。更に燃料装荷かご2を矢印Bのように上
方へ吊り上げると、燃料装荷かごの上部は矢印Cに示す
ように、被覆管取出口4へ倒れ込み中の被覆管が取り出
される。
The fuel loading basket lifting device 6 descends, and the fuel loading basket gripping device 5 grips the fuel loading basket 2 disposed in the melting tank 1 at a position closer to the bottom than the center of gravity. Next, the fuel loading car lift device 6 lifts up the fuel loaded basket 2 and transports it to the cladding pipe removal section 9. FIG. 2(b) is a sectional view showing the operation of the fuel loading cap 2 falling into the cladding tube outlet 4. The gripping part 10 of the fuel loading basket gripping device 5 is configured to hold a fuel loading basket 2.
Is it times? Since it has a mechanism that allows it to move freely, depending on the balance between fuel loading and 2, the center of gravity position 1 can be adjusted as shown by the arrow.
1 moves. Further, when the fuel loading basket 2 is lifted upward as shown by arrow B, the upper part of the fuel loading basket collapses into the cladding tube outlet 4 as shown by arrow C, and the cladding tube that is falling down is taken out.

第3図は、燃料装荷かと2のバランスにより被覆管取出
口4と反対側へ倒れた場合、又は、どちらへも倒れなか
った場合の動作を示す断面図である。
FIG. 3 is a sectional view showing the operation when the cladding tube falls to the side opposite to the cladding tube outlet 4 due to the balance between the fuel loading and the cladding tube 2, or when it does not fall in either direction.

燃料装荷かご昇降袋[6により燃料装荷かご2を上昇さ
せると、第3図(a)の破線に示すように、燃料装荷か
ご2の上端がガイド板7に接触する。更に矢印りに示す
ように上昇させると、燃料装荷かと2の上端がガイド板
7の形状に沿って移動する。第3図(b)の破線で示し
たように燃料装荷かご2が傾くと、矢印Eに示すように
重心位置11が重力により回動し、燃料装荷かと2の上
部が被覆管取出口4内へ倒れ込む。以後は、第2図(b
)と同様の動作により、被m管を取出すことができる。
When the fuel loading car 2 is raised by the fuel loading car lift bag [6, the upper end of the fuel loading car 2 comes into contact with the guide plate 7, as shown by the broken line in FIG. 3(a). When further raised as shown by the arrow, the upper end of the fuel loading lever 2 moves along the shape of the guide plate 7. When the fuel loading basket 2 is tilted as shown by the broken line in FIG. Fall down. From now on, Figure 2 (b
) The tube to be covered can be taken out by the same operation as in ).

ガイド板の形状は、燃料装荷かご2を必ず被覆管取出口
4の側へ押し戻す構造であれば良い。また、このガイド
板の代わりに、燃料装荷かと2に、駆動機構を用いて押
し戻す動作を加えることによる方法でも良い。
The guide plate may have any shape as long as it always pushes the fuel loading basket 2 back toward the cladding tube outlet 4 side. Further, instead of using this guide plate, a method may be used in which a driving mechanism is used to push back the fuel loading lever 2.

第4図は、押し戻し装@12の一例を示す断面図である
。この例では、押し戻し部13が押し戻し駆動装置14
により、矢印Fのような動作を行い、これにより、燃料
装荷かと2が被覆管取出口4側へ傾くものである。
FIG. 4 is a sectional view showing an example of the push-back device @12. In this example, the push-back section 13 is the push-back drive device 14.
As a result, an operation as shown by arrow F is performed, and as a result, the fuel loading lever 2 is tilted toward the cladding tube outlet 4 side.

第5図は燃料装荷かと2を把持する部分の一実施例を示
す断面図である。燃料装荷かと2の重心位置よりも底部
に近い位置の側面に、把持部材15を接合し、その上に
円形の把持穴16を開ける。把持穴16は、両側の面に
各1ケ所ずつ設け、2つの把持穴16の中心は同じ高さ
に位置するものとする。すなわち、第5図中の直線QQ
’上に両側の把持穴】6の中心が存在するようにする。
FIG. 5 is a sectional view showing an embodiment of a portion that grips the fuel loading lever 2. FIG. A gripping member 15 is joined to the side surface of the fuel loading cap 2 at a position closer to the bottom than the center of gravity, and a circular gripping hole 16 is bored thereon. One gripping hole 16 is provided on each side, and the centers of the two gripping holes 16 are located at the same height. In other words, the straight line QQ in Figure 5
'Grip holes on both sides] Make sure the center of 6 is on the top.

第6図は燃料装荷かご把持装置5の把持部の構造の一実
施例を示す断面図である。把持アーム17の先端に円錐
系の把持ツメ18があり、把持アーム17が矢印Gのよ
うに開閉することにより、燃料装荷かと2を把持する。
FIG. 6 is a sectional view showing an embodiment of the structure of the gripping portion of the fuel loading basket gripping device 5. As shown in FIG. There is a conical gripping claw 18 at the tip of the gripping arm 17, and when the gripping arm 17 opens and closes as shown by arrow G, it grips the fuel loading valve 2.

把持した時、把持ツメ18は把持穴16の中に入るが、
若干の余裕をもたせることにより、把持部を中心に燃料
装荷かと2が回動自在となる。把持穴16には図示のよ
うにテーパを持たせると、把持ツメ18が挿入し易く、
回IJjに耐える強度が確保できる。把持穴IGの位置
は燃料装荷かと2の重心位置より底部に近ければ良いの
で、燃料装荷かと2の上部を重くすることにより、把持
アーム17の長さを短くすることができる。把持アーム
17の開閉動作は、この例ではアクチュエータ22のシ
ャフト21の回転をウオーム19及びウオームホイール
20に伝えることにより行われる。
When gripped, the gripping claw 18 enters the gripping hole 16, but
By providing a slight margin, the fuel loading lever 2 can rotate freely around the grip. If the grip hole 16 is tapered as shown, the grip claw 18 can be easily inserted.
The strength to withstand times IJj can be ensured. Since the position of the gripping hole IG needs to be closer to the bottom than the center of gravity of the fuel loading cap 2, the length of the gripping arm 17 can be shortened by making the upper part of the fuel loading cap 2 heavier. In this example, the opening/closing operation of the gripping arm 17 is performed by transmitting the rotation of the shaft 21 of the actuator 22 to the worm 19 and the worm wheel 20.

燃料装荷かご昇降装置6を該燃料装荷がご2の位置まで
移動するためには、■該燃料装荷がと2の方を移動させ
る方法、■燃料装荷がご昇降装置6の方を移動させる方
法、あるいは、G)その両者を部分的に移動させるなど
の方法で行なうことができる。
In order to move the fuel loading car lifting device 6 to the position of the fuel loading car 2, there are two methods: (1) a method of moving the fuel loading car (2), and (2) a method of moving the fuel loading car lifting device 6 (6). , or G) by partially moving both of them.

第3番目の方法の一実施例について第7図により説明す
る。第7図は、連続溶解処理装置における燃料装荷かご
2の移動状態を示すものである。溶解槽1の中の燃料装
荷かご2は、環状の吊下げ板23により保持されており
、一定時間ごとに順次一方向へ回転する。回転は、吊下
げ板回転駆動装置24により行われる。溶解一槽1には
隔壁26があり、これとしきり板27との間の燃料装荷
かご1個分のスペースに設置された供給口29から硝酸
が供給され、隔壁26の反対側に設置された排出口30
から燃料が溶解した溶解処理液3が排出される。この装
置において、矢印のように燃料装荷かと2を移動させる
ことにより、連続溶解が可能となる。図中の0部で燃料
装荷かと2を取り出して1部へ運搬し、ここで被覆管を
取り出して3部で再び溶解槽1内に入れ、新たに燃料剪
断片を装荷する。図中において、ジャケット底25によ
り、溶解処理液3は加熱される。
An embodiment of the third method will be described with reference to FIG. FIG. 7 shows the moving state of the fuel loading basket 2 in the continuous melting treatment apparatus. The fuel loading basket 2 in the melting tank 1 is held by an annular hanging plate 23, and rotates in one direction at regular intervals. The rotation is performed by a hanging plate rotation drive device 24. The melting tank 1 has a partition wall 26, and nitric acid is supplied from a supply port 29 installed in a space for one fuel loading basket between this and a partition plate 27, which is installed on the opposite side of the partition wall 26. Discharge port 30
A dissolving treatment liquid 3 in which fuel is dissolved is discharged from the tank. In this device, continuous melting is possible by moving the fuel loading 2 as shown by the arrow. At part 0 in the figure, the fuel loaded part 2 is taken out and transported to part 1, where the cladding tube is taken out and part 3 is put into the melting tank 1 again, and a fuel sheared piece is newly loaded. In the figure, the dissolving treatment liquid 3 is heated by the jacket bottom 25.

第7図の連続溶解方式における本発明の連続溶解処理装
置の一例を第8図により説明する。溶解槽lは、完全に
カバー8で覆われ、気密性が保持される。第7図におけ
るH、I、3部もカバー8で密封されており、被覆管取
出口4が接続されている。
An example of the continuous melting treatment apparatus of the present invention using the continuous melting method shown in FIG. 7 will be explained with reference to FIG. 8. The dissolution tank 1 is completely covered with a cover 8 to maintain airtightness. Sections H, I, and 3 in FIG. 7 are also sealed with covers 8, and are connected to the cladding tube outlet 4.

燃料装荷かご昇降装置6は、燃料装荷かご把持装置5を
吊り下げた状態で、カバー8に取付けられ、水平移動装
置2Bによりカバー8上を矢印にで示すように移動する
。これにより、燃料装荷かご2の移動及び被覆管の取出
しが可能となる。
The fuel loading basket lifting device 6 is attached to the cover 8 with the fuel loading basket gripping device 5 hanging thereon, and is moved on the cover 8 by the horizontal moving device 2B as shown by the arrow. This makes it possible to move the fuel loading basket 2 and take out the cladding tube.

本発明の実施例によれば、被覆管の取出し及び連続溶解
を実現するために不可欠な燃料装荷かごの移動に必要な
駆動機構が少なく、駆動部に要する保守の頻度が低くな
る。また、駆動部は溶解槽1上のカバー8に取り付けら
れており、カバ〜8を一部分取外すことにより、容易に
交換可能となり。
According to embodiments of the present invention, fewer drive mechanisms are required to move the fuel loading basket, which is essential to achieve cladding removal and continuous melting, and the frequency of maintenance required for the drive is reduced. Further, the drive unit is attached to a cover 8 on the dissolution tank 1, and can be easily replaced by partially removing the cover 8.

マニプレータ等の遠隔操作による保守が可能となるので
、保守に要する時間及び保守作業員の放射線被ばくの低
減が図られる。更に、コンパクトな形状で実現できるた
め、使用済原子燃料再処理施設における溶解処理段mの
スペースが小さくて済み、また、溶解処理装置の気密性
を保持するためにカバーで全体を覆うことができるため
、放射能汚染の拡大を防ぐことができる。
Since maintenance can be performed by remote control of the manipulator, etc., the time required for maintenance and the radiation exposure of maintenance workers can be reduced. Furthermore, since it can be realized in a compact shape, the space required for the melting treatment stage m in the spent nuclear fuel reprocessing facility is small, and the entire melting treatment equipment can be covered with a cover to maintain its airtightness. Therefore, the spread of radioactive contamination can be prevented.

[発明の効果] 本発明によれば、重力を利用することにより、被覆管取
出しに必要な駆動部分が少なくて済み、保守頻度を低減
できるという効果がある。また、簡略な構造であり、か
つ、カバーの一部を取外すことで駆動部を交換できるた
め、保守が容易であり、マニプレータ等での遠隔保守も
可能であるため、保守時間の削減及び保守作業員の被ば
く低減の効果がある。また、コン゛バク1−な空間で被
覆管取出しが可能であり、溶解処理装置全体の気密性を
損うことがないので、放射能による汚染拡大を防ぐこと
ができる。
[Effects of the Invention] According to the present invention, by utilizing gravity, fewer driving parts are required to take out the cladding tube, and maintenance frequency can be reduced. In addition, the structure is simple and the drive unit can be replaced by removing part of the cover, making maintenance easy. Remote maintenance using a manipulator, etc. is also possible, reducing maintenance time and maintenance work. This has the effect of reducing radiation exposure for personnel. Further, the cladding tube can be taken out in a compact space, and the airtightness of the entire melting treatment apparatus is not impaired, so that it is possible to prevent the spread of contamination due to radioactivity.

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

第1図は本発明の一実施例の使用済原子燃料の連続溶解
処理装置の断面図、第2図ないし第4図は第1図の装置
における被覆管取出し部分の断面図、第5図は燃料装荷
かごの斜視図、第6図は燃料装荷かご把持装置の一例を
示す一部断面図、第7図は連続溶解処理装置における燃
料装荷かごの移動動作説明図、第8図は第7図の動作時
における本発明の一実施例を示す連続溶解処理装置の斜
視図である。 1・・・溶解槽、2・・・燃料装荷かと、3・・・溶解
処理液、4・・・被覆管取出口、5・・・燃料装荷かご
把持装置、6・・・燃料装荷かご昇降装置、7・・・ガ
イド板、8・・・カバー、9・・・被覆管取出部、10
・・・把持部、11・・重心位置、12・・・押し戻し
装置、13・・・押し戻し部、14・・・押し戻し駆動
装置、15・・・把持部材、16・・・把持穴、17・
・・把持アーム、18・・・把持ツメ、23・・・吊下
げ板、24・・・吊下げ板回転駆動装置、25・・・ジ
ャケット底、26・・・隔壁、27・・・しきり板、2
8・・・水平移動装置、29・・Cb) 第4図 第5区 第6 口 Z4 第 [
FIG. 1 is a cross-sectional view of a continuous melting treatment device for spent nuclear fuel according to an embodiment of the present invention, FIGS. 2 to 4 are cross-sectional views of the cladding pipe extraction portion of the device in FIG. 1, and FIG. A perspective view of a fuel loading basket, FIG. 6 is a partial cross-sectional view showing an example of a fuel loading basket gripping device, FIG. 1 is a perspective view of a continuous dissolution processing apparatus showing an embodiment of the present invention during operation. DESCRIPTION OF SYMBOLS 1...Dissolution tank, 2...Fuel loading, 3...Dissolution treatment liquid, 4...Claying tube outlet, 5...Fuel loading basket gripping device, 6...Fuel loading basket lifting/lowering Device, 7... Guide plate, 8... Cover, 9... Cladding tube removal part, 10
... Gripping part, 11... Center of gravity position, 12... Pushing back device, 13... Pushing back portion, 14... Pushing back drive device, 15... Gripping member, 16... Gripping hole, 17...
... Gripping arm, 18... Gripping claw, 23... Hanging plate, 24... Hanging plate rotation drive device, 25... Jacket bottom, 26... Bulkhead, 27... Shikiri plate ,2
8...Horizontal movement device, 29...Cb) Figure 4 Section 5 No. 6 Exit Z4 No. [

Claims (1)

【特許請求の範囲】 1、(a)溶解処理液を充填し、かつ使用済原子燃料を
溶解するための円形状の溶解槽、(b)使用済原子燃料
を装荷し、かつ前記溶解槽内に浸漬するためのものであ
って該溶解槽内に並べて配置された複数個の燃料装荷か
ご、(c)該燃料装荷かごを溶解槽から出し入れするた
めの燃料装荷かご把持装置を備えた燃料装荷かご昇降装
置、(d)不溶解燃料被覆管の取出口、(e)溶解処理
液の供給口及び(f)排出口を含む溶解処理装置におい
て、前記燃料装荷かご昇降装置に備えられた燃料装荷か
ご把持装置は、使用済原子燃料溶解処理終了後における
不溶解燃料被覆管を含む燃料装荷かご全体の重心位置よ
りも下部の位置において回動自在に把持するように構成
することにより該燃料装荷かごを上昇させたとき該燃料
装荷かごが自動的に転倒し、上部の開口部が下向きにな
るようにして内部の不溶解燃料被覆管を前記不溶解燃料
被覆管の取出口に排出できるように構成したことを特徴
とする使用済原子燃料の連続溶解処理装置。 2、前記燃料装荷かごの上部開口部が前記不溶解燃料被
覆管の取出口の方に向くように該燃料装荷かごの昇降経
路の一部に該燃料装荷かごを押圧する手段を設けたこと
を特徴とする特許請求の範囲第1項記載の使用済原子燃
料の連続溶解処理装置。 3、前記押圧手段がガイド板であることを特徴とする特
許請求の範囲第2項記載の使用済原子燃料の連続溶解処
理装置。
[Claims] 1. (a) a circular dissolution tank filled with a dissolution treatment liquid and for dissolving spent nuclear fuel; (b) a circular dissolution tank filled with a dissolution treatment liquid and for dissolving spent nuclear fuel; (c) a fuel loading basket provided with a fuel loading basket gripping device for taking the fuel loading baskets in and out of the melting tank; A car lifting device, (d) an outlet for undissolved fuel cladding, (e) a supply port for a dissolution treatment liquid, and (f) a discharge port, in the melting treatment device, the fuel loading device provided in the fuel loading car lifting device. The basket gripping device is configured to rotatably grip the fuel loading basket at a position lower than the center of gravity of the entire fuel loading basket including the undissolved fuel cladding after the spent nuclear fuel melting process is completed. When the fuel loading basket is raised, the fuel loading basket is automatically tipped over so that the opening at the top faces downward, so that the internal undissolved fuel cladding tube can be discharged to the outlet of the undissolved fuel cladding tube. A continuous melting and processing device for spent nuclear fuel, which is characterized by: 2. A means for pressing the fuel loading basket is provided in a part of the lifting path of the fuel loading basket so that the upper opening of the fuel loading basket faces the outlet of the insoluble fuel cladding tube. A continuous melting and processing apparatus for spent nuclear fuel according to claim 1. 3. The continuous melting treatment apparatus for spent nuclear fuel according to claim 2, wherein the pressing means is a guide plate.
JP15122187A 1987-06-19 1987-06-19 Continuous spent fuel processing equipment Expired - Fee Related JPH0658430B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP15122187A JPH0658430B2 (en) 1987-06-19 1987-06-19 Continuous spent fuel processing equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP15122187A JPH0658430B2 (en) 1987-06-19 1987-06-19 Continuous spent fuel processing equipment

Publications (2)

Publication Number Publication Date
JPS63315994A true JPS63315994A (en) 1988-12-23
JPH0658430B2 JPH0658430B2 (en) 1994-08-03

Family

ID=15513894

Family Applications (1)

Application Number Title Priority Date Filing Date
JP15122187A Expired - Fee Related JPH0658430B2 (en) 1987-06-19 1987-06-19 Continuous spent fuel processing equipment

Country Status (1)

Country Link
JP (1) JPH0658430B2 (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6111929U (en) * 1984-06-13 1986-01-24 荏原インフイルコ株式会社 Adsorbent cartridge
JPS61169798A (en) * 1985-01-23 1986-07-31 株式会社日立製作所 Continuous melter for spent nuclear fuel

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6111929U (en) * 1984-06-13 1986-01-24 荏原インフイルコ株式会社 Adsorbent cartridge
JPS61169798A (en) * 1985-01-23 1986-07-31 株式会社日立製作所 Continuous melter for spent nuclear fuel

Also Published As

Publication number Publication date
JPH0658430B2 (en) 1994-08-03

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