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JPH07122680B2 - Main structure of continuous reactor for nuclear fuel - Google Patents
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JPH07122680B2 - Main structure of continuous reactor for nuclear fuel - Google Patents

Main structure of continuous reactor for nuclear fuel

Info

Publication number
JPH07122680B2
JPH07122680B2 JP22078786A JP22078786A JPH07122680B2 JP H07122680 B2 JPH07122680 B2 JP H07122680B2 JP 22078786 A JP22078786 A JP 22078786A JP 22078786 A JP22078786 A JP 22078786A JP H07122680 B2 JPH07122680 B2 JP H07122680B2
Authority
JP
Japan
Prior art keywords
nuclear fuel
upper lid
annular container
peripheral side
annular
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 - Fee Related
Application number
JP22078786A
Other languages
Japanese (ja)
Other versions
JPS6375596A (en
Inventor
明 井上
泰宏 佐々田
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 JP22078786A priority Critical patent/JPH07122680B2/en
Publication of JPS6375596A publication Critical patent/JPS6375596A/en
Publication of JPH07122680B2 publication Critical patent/JPH07122680B2/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

Landscapes

  • Gasification And Melting Of Waste (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Cleaning And De-Greasing Of Metallic Materials By Chemical Methods (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、使用済み核燃料の連続溶解処理装置に係り、
特に溶解槽内部の気密性をよくするのに好適な核燃料連
続溶解処理装置の本体構造に関する。
TECHNICAL FIELD The present invention relates to a continuous melting and treating apparatus for spent nuclear fuel,
In particular, the present invention relates to a main body structure of a nuclear fuel continuous dissolution treatment apparatus suitable for improving airtightness inside a dissolution tank.

〔従来の技術〕[Conventional technology]

一般に、使用済み核燃料の溶解処理装置には、(i)回
分式溶解装置、(ii)半連続式溶解装置、(iii)連続
式溶解装置の3種類に大別することができる。
Generally, spent nuclear fuel melting treatment apparatuses can be roughly classified into three types: (i) batch type melting apparatus, (ii) semi-continuous melting apparatus, and (iii) continuous melting apparatus.

しかるに、前記(i)の回分式溶解装置では、溶解液を
保持した溶解装置に、1バツチ分の剪断片を装荷し溶解
させ、溶解完了後、溶解液を抜き出し被覆材(ハル)を
すすぎ、溶解装置から取り出し、操作を終了するように
している。この装置の特長は、装置の構成が単純なこと
であるが、半面、容量の割に装置が大型になつてしまう
欠点がある。
However, in the batch type dissolution apparatus of the above (i), the dissolution apparatus holding the dissolution solution is loaded with one batch of shear fragments and dissolved, and after the dissolution is completed, the dissolution solution is extracted and the coating material (hull) is rinsed, The operation is completed by taking it out from the melting device. The feature of this device is that the structure of the device is simple, but on the other hand, there is a drawback that the device becomes large for its capacity.

一方、(ii)の半連続式溶解装置では、溶解液を保持し
た溶解装置に、剪断片を一定速度で装荷し、同時に溶解
液を新しい溶解液と置換排出して、1バツチ分の前断片
の装荷が終わり溶解完了後、ハルをすすぎ、溶解装置か
ら取り出し、操作を終わるようにしている。この装置の
特長は、前記回分式溶解装置に比べ、装置の構成は複雑
となるが、小型化が可能となる。
On the other hand, in the semi-continuous dissolution apparatus (ii), a shear fragment is loaded at a constant rate on the dissolution apparatus holding the dissolution solution, and at the same time, the dissolution solution is replaced with a new dissolution solution and discharged to remove one fragment of the previous fragment. After the loading is completed and the melting is completed, the hull is rinsed, taken out from the melting device, and the operation is finished. The advantage of this apparatus is that the apparatus has a more complicated structure than the batch-type dissolving apparatus, but can be downsized.

さらに、前記(iii)の連続式溶解装置では、剪断片と
溶解液を連続的に溶解装置に装荷し、溶解液とハルを連
続的に取り出すようにしている。この装置では、回分式
でみられる溶解初期における急激な溶解反応を防止する
ことができ、装置をより小型化することができるという
利点がある。
Further, in the continuous dissolution apparatus of (iii) above, the sheared fragment and the dissolution liquid are continuously loaded into the dissolution device, and the dissolution liquid and the hull are continuously taken out. This device has an advantage that it is possible to prevent a rapid dissolution reaction at the initial stage of dissolution that is seen in a batch system, and to make the device more compact.

ところで、この連続式溶解装置の従来例としては、特公
昭60−41318号公報に開示されている。腐食性液中での
処理物の連続処理装置が知られている。この装置は、直
立式環状容器を使用し、容器内周に沿つて複数の核燃料
装荷かごを配置し、順次一方向に回転させ、下方にきた
かごを溶解処理液に浸すよう構成している。
By the way, a conventional example of this continuous melting apparatus is disclosed in Japanese Patent Publication No. 60-41318. There is known a continuous treatment device for treating substances in a corrosive liquid. This apparatus uses an upright annular vessel, and arranges a plurality of nuclear fuel-loaded cages along the inner circumference of the vessel and sequentially rotates them in one direction so that the cages below are immersed in the dissolution treatment solution.

〔発明が解決しようとする課題〕[Problems to be Solved by the Invention]

しかしながら、上述のように構成された従来の連続式溶
解装置においては、駆動に際して駆動部金属間の接触が
溶解液(硝酸)中で生じ、その結果、駆動部が腐食する
原因となつていた。また、従来は直立型であるため、耐
震上不利であるという欠点もあつた。
However, in the conventional continuous melting apparatus configured as described above, when driving, contact between the metal parts of the drive part occurs in the solution (nitric acid), and as a result, the drive part is corroded. Moreover, since it has been an upright type in the past, it is disadvantageous in terms of earthquake resistance.

尚、特開昭61−169798号公報に記載の連続溶解装置は、
発揮性の腐食性処理溶液に対する配慮に欠け、駆動部が
腐食性処理溶液の雰囲気にさらされ、また、環状容器の
内外はガスケットにより気密化されているため、ガスケ
ットの損傷により腐食性ガスが環状容器外へ漏洩する恐
れがあった。
Incidentally, the continuous dissolution apparatus described in JP-A-61-169798,
Due to lack of consideration for demonstrable corrosive treatment solution, the drive part is exposed to the atmosphere of corrosive treatment solution, and the gasket inside and outside of the annular container is hermetically sealed. There was a risk of leaking out of the container.

本発明は、上述した問題点に鑑みなされたもので、駆動
部が発揮性の腐食性処理溶液の雰囲気に接するのを確実
に防止できるようにし、かつ腐食性ガスが容器外へ漏洩
する恐れのない、安全性及びメンテナンスに優れた核燃
料連続溶解装置の本体構造を提供することを目的とする
ものである。
The present invention has been made in view of the above-mentioned problems, and it is possible to reliably prevent the drive unit from coming into contact with the atmosphere of the volatile corrosive treatment solution, and the corrosive gas may leak out of the container. It is an object of the present invention to provide a main body structure of a nuclear fuel continuous melting apparatus which is excellent in safety and maintenance.

〔課題を解決するための手段〕[Means for Solving the Problems]

上記目的を達成するために本発明は、 腐食性を有する溶解処理液を保持し、上部に上蓋を
備える水平式環状容器の内部に、ローラにより駆動支持
された環状壁状の吊下げ板に複数個の核燃料装荷かごを
吊下げて配置するとともに、前記核燃料を装架したかご
の一定高さを前記溶解処理液に浸漬しつつ、前記吊下げ
板の円環状の移動により前記かごを順次一方向に移動さ
せて核燃料を溶解する核燃料連続溶解装置の本体構造に
おいて、 前記吊下げ板の下部と前記環状容器との間、及び、
前記吊下げ板の上部と前記上蓋との間のそれぞれに、気
密性を保持して前記吊下げ板が移動可能な第1及び第2
の水シールが設けられているとともに、 前記環状容器の内周側及び外周側の前記上蓋との接
触部には、前記環状容器側に凹部を、かつ前記上蓋側に
前記凹部に嵌合する凸部を設け、前記内周側及び外周側
のそれぞれの凹凸部に、気密性を維持する第3及び第4
の水シールが設けられ、 かつ、前記環状容器の上部を塞ぐ上蓋を一体構造に
して、前記環状容器と前記上蓋とのボルト締付固定部
を、前記第4の水シールより外周側に設けたことを特徴
とするものである。
In order to achieve the above-mentioned object, the present invention holds a corrosive dissolution treatment solution, and a plurality of annular wall-shaped suspension plates driven and supported by rollers inside a horizontal annular container having an upper lid on the top. While arranging individual nuclear fuel loaded cars in a suspended manner, and immersing a fixed height of the car on which the nuclear fuel is mounted in the dissolution treatment solution, the cars are sequentially moved in one direction by circular movement of the suspension plate. In the main body structure of the nuclear fuel continuous melting apparatus for moving the nuclear fuel to dissolve the nuclear fuel, between the lower portion of the suspension plate and the annular container, and
First and second movable airtight suspension plates are provided between the upper portion of the suspension plate and the upper lid, respectively, while maintaining airtightness.
The water seal is provided, and at the contact portion with the upper lid on the inner peripheral side and outer peripheral side of the annular container, a concave portion is fitted on the annular container side and a convex portion is fitted on the upper lid side. Third and fourth portions that are provided with air-tightness on the inner peripheral side and the outer peripheral side respectively.
Water seal is provided, and the upper lid that closes the upper portion of the annular container has an integral structure, and the bolt tightening and fixing portion of the annular container and the upper lid is provided on the outer peripheral side of the fourth water seal. It is characterized by that.

〔作用〕[Action]

上記構成によれば、核燃料装荷かごを吊下げて移動する
吊下げ板が、気密性を保持しているため、吊下げ板を駆
動支持するローラを腐食性溶液の雰囲気から気密的に隔
離るることができ、ローラの摩耗及び損傷を防止するこ
とができる。また、環状容器内部と外部との間は、吊下
げ板の第1及び第2の水シールと、環状容器外周側の第
4の水シールとにより2重にシールされ、気密性の維持
がより一層向上するとともに、シール部の凹凸高さを緩
和できるのて構造が容易となる。しかも、上蓋の一体構
造により気密性が維持しやすく、上蓋のボルト締付固定
部を、最外周にすることにより、ボルト部の腐食を防止
し、かつ気密性の維持が有利である。
According to the above configuration, since the suspension plate that moves by suspending the nuclear fuel-loaded basket retains airtightness, the roller that drives and supports the suspension plate is airtightly isolated from the atmosphere of the corrosive solution. It is possible to prevent wear and damage of the roller. Further, between the inside and the outside of the annular container is double-sealed by the first and second water seals of the hanging plate and the fourth water seal on the outer peripheral side of the annular container, so that the airtightness is more maintained. The structure is further improved because the height of the unevenness of the seal portion can be alleviated as well as further improved. In addition, the airtightness can be easily maintained by the integral structure of the upper lid, and by making the bolt tightening and fixing portion of the upper lid the outermost periphery, it is advantageous to prevent the corrosion of the bolt portion and to maintain the airtightness.

〔実施例〕〔Example〕

以下、図に示す実施例を用いて本発明の詳細を説明す
る。
The present invention will be described in detail below with reference to the embodiments shown in the drawings.

第1図は本発明に係る核燃料連続溶解処理装置の一実施
例を示す全体構成図、第2図は第1図の装置の本体部の
要部拡大断面図、第3図は第1図の装置の本体部の要部
拡大斜視図である。水平式環状容器1の内部には、溶解
液3として硝酸があるレベルの液面4まで満されてい
る。使用済み燃料剪断片8を装入する燃料装荷かご2
は、燃料装荷かご吊下げ板14に吊下げられ、一定の高さ
まで溶解液3に浸るようになつている。この吊下げ板14
は、吊下げ板支持ローラ15に支持された状態で、矢印y
方向に回転するよう構成されている。前記環状容器1内
では、硝酸である溶解液3による燃料の溶解で、発揮性
のFP(核分裂生成物)および硝酸が気相中に出てくるの
で、上蓋5で密封されるようになつている。この上蓋5
は、環状容器1にボルト6により固定されるとともに、
容器内部を負圧にして、硝酸の外部への漏洩を防いでい
る。
FIG. 1 is an overall configuration diagram showing an embodiment of a nuclear fuel continuous dissolution treatment apparatus according to the present invention, FIG. 2 is an enlarged cross-sectional view of an essential part of a main body of the apparatus of FIG. 1, and FIG. 3 is of FIG. It is a principal part expansion perspective view of the main-body part of an apparatus. The horizontal annular container 1 is filled with a liquid level 4 at a level at which nitric acid as a solution 3 is present. Fuel-loading basket 2 for loading spent fuel shears 8
Is suspended on a fuel-carrying car suspension plate 14 so that it can be immersed in the solution 3 up to a certain height. This hanging plate 14
Is supported by the hanging plate support roller 15, and the arrow y
Is configured to rotate in a direction. In the annular vessel 1, the FP (fission products) and nitric acid, which are active, come out in the gas phase due to the dissolution of the fuel by the solution 3 which is nitric acid, so that the upper lid 5 is sealed. There is. This top lid 5
Is fixed to the annular container 1 with bolts 6,
Negative pressure is applied inside the container to prevent nitric acid from leaking to the outside.

ここで、さらに気密性を上げるために、水シール16,17
を使用する。また、吊下げ板支持ローラ15のような機械
部分が硝酸雰囲気下で腐食,劣化するのを防ぐために、
ローラ保護用水シール18を使用するようにしている。こ
のとき、燃料装荷かご吊下げ板14の内側(駆動部)と外
側では、差圧を大きくする必要がない。つまり、差圧が
小さくても水シール16,17が存在するからである。した
がつて、10〜20mmHgとすれば、ローラ保護用水シール18
の凹凸部の高さは、約10cmあれば差圧を保つのに十分で
ある。環状容器1の内部と外部では、差圧が100mmHg前
後に達する可能性があるので、内周側水シール16は必要
であり、外周側水シール17とも凹凸部の高さは、約20cm
あれば十分である。
Here, in order to further increase the airtightness, the water seal 16,17
To use. Further, in order to prevent mechanical parts such as the hanging plate supporting roller 15 from being corroded or deteriorated in a nitric acid atmosphere,
A roller protection water seal 18 is used. At this time, it is not necessary to increase the pressure difference between the inside (driving portion) and the outside of the fuel-loaded car suspension plate 14. That is, the water seals 16 and 17 are present even if the differential pressure is small. Therefore, if the pressure is 10 to 20 mmHg, the water seal for roller protection 18
The height of the uneven portion of about 10 cm is enough to maintain the differential pressure. The pressure difference between the inside and outside of the annular container 1 may reach around 100 mmHg, so the inner water seal 16 is necessary, and the outer water seal 17 has a height of 20 cm.
It is enough.

前記水シール16,17,18とも水補給用配管19により水が補
給され、シール部分が水20に浸されるようになつてお
り、このため長期間の運転も可能である。
The water seals 16, 17, 18 are replenished with water by the water replenishing pipe 19 so that the sealed portions are immersed in the water 20, and therefore, long-term operation is also possible.

前記環状容器1の内部には、複数個の同一形状を有する
燃料装荷かご2が装荷されており、このかごの2の中に
は、使用済み燃料剪断片8が装入されるよう構成されて
いる。燃料装荷かご2は、燃料装荷かご吊下げ板14によ
り保持され、吊下げ板14は、吊下げ板支持ローラ15によ
り支持され、回転駆動装置により反時計方向へ回転する
よう構成されている。しかるに、使用済み燃料は、溶解
液3中に溶解していき、溶解の完了した燃料装荷かご2
は、環状容器1の燃料装荷かご取出扉10のある部分で停
止するようなつている。ここで、この取出扉10が開か
れ、燃料装荷かご2を吊上げ装置9で溶解液3中から洗
浄室21へ取り出したのち、再び取出扉10が閉じられる。
洗浄室21では、スプレーノズル11で水を噴出させて燃料
装荷かご2を洗浄するようになつている。さらに、洗浄
された燃料装荷かご2は、搬出入装置12により連続溶解
処理装置外部へ搬出され、ハルをハル回収容器13へ廃棄
するようになつている。
A plurality of fuel-loaded cages 2 having the same shape are loaded inside the annular container 1, and a spent fuel shearing piece 8 is loaded into the cage 2. There is. The fuel loaded car 2 is held by a fuel loaded car suspension plate 14, the suspension plate 14 is supported by a suspension plate support roller 15, and is configured to rotate counterclockwise by a rotation drive device. However, the spent fuel dissolves in the solution 3 and the dissolved fuel-loaded basket 2
Is configured to stop at a portion of the annular container 1 where the fuel loading car extraction door 10 is located. Here, the take-out door 10 is opened, the fuel-loaded car 2 is taken out from the solution 3 into the cleaning chamber 21 by the lifting device 9, and then the take-out door 10 is closed again.
In the cleaning chamber 21, the spray nozzle 11 sprays water to clean the fuel-loaded car 2. Further, the washed fuel-loaded car 2 is carried out of the continuous dissolution processing device by the carry-in / carry-out device 12, and the hull is discarded in the hull collection container 13.

ところで、溶解装置では、使用済み燃料を溶解するため
に、燃料棒の剪断片8が装荷され、溶解液(硝酸)3に
より溶解される。使用済み燃料の放射能の大部分はFP
(核分裂生成物)であり、炉取り出し後約1年間経過し
たあとでも、106ci/tのオーダを持つので、装置内の放
射能レベルが非常に高く、FPが外部に漏れないように負
圧にしておく。そのため、気密性が悪いと外部から空気
が入り込み、装置内の排気用設備の負荷を著しく増加さ
せることになる。
By the way, in the melting apparatus, in order to dissolve the spent fuel, the shear pieces 8 of the fuel rod are loaded and melted by the dissolving liquid (nitric acid) 3. Most of the radioactivity of spent fuel is FP
Since it is a fission product and has an order of 10 6 ci / t even after about 1 year has passed since the reactor was taken out, the radioactivity level inside the device is extremely high and it is negative so that FP does not leak outside. Keep pressure. Therefore, if the airtightness is poor, air will enter from the outside, and the load on the exhaust equipment in the apparatus will be significantly increased.

そこで、装置本体上蓋を分割できる構造にすると、組み
立てたときシールする箇所が増えて気密性が悪くなる。
そこで、本実施例のように、上蓋5を一体化構造にすれ
ば、シールの必要な箇所は環状容器1と上蓋5の接触部
分に限られ、気密性を維持しやすい。メインテナンス時
においても、分割型に比べ、広い作業スペースを必要と
するが、一方作業効率は上がる。
Therefore, if the upper lid of the main body of the apparatus is configured to be separable, more parts will be sealed when assembled and the airtightness will deteriorate.
Therefore, if the upper lid 5 is formed into an integrated structure as in the present embodiment, the portion requiring sealing is limited to the contact portion between the annular container 1 and the upper lid 5, and the airtightness can be easily maintained. Even during maintenance, it requires a larger work space than the split type, but on the other hand, work efficiency is improved.

また、硝酸雰囲気下で腐食性も強いので、気密性を保つ
ために、シールは高放射能,腐食,熱変形に耐え、メイ
ンテナンスの容易なものでなければならない。したがつ
て、高分子樹脂、ゴム等の固体状シールは、破損あるい
は劣化したときに交換が容易でなく、放射化された固体
廃棄物としての発生量を増加させることになる。
Also, since it is highly corrosive in a nitric acid atmosphere, in order to maintain airtightness, the seal must be resistant to high radioactivity, corrosion and thermal deformation, and easy to maintain. Therefore, the solid seal made of polymer resin, rubber or the like is not easy to replace when it is broken or deteriorated, which increases the amount of radioactive solid waste generated.

一方、水シールは、溶解装置内の減圧が100mmHg前後な
ら構造的に使用容易であり、耐放射線性,耐腐食性があ
り、液体状なので固体シールのような破損および劣化の
可能性はなく、稼動部分のシールも可能である。また、
メインテナンスも容易であり、水が補給用配管19により
補給されれば、長期間の使用にも耐えうるという効果を
有する。
On the other hand, the water seal is structurally easy to use if the decompression inside the melting device is around 100 mmHg, has radiation resistance and corrosion resistance, and since it is liquid, there is no possibility of damage and deterioration like a solid seal, It is also possible to seal the moving parts. Also,
Maintenance is easy, and if water is supplied through the supply pipe 19, it has the effect that it can withstand long-term use.

また、本発明置装は、水平式環状容器1を採用してお
り、従来の直立型に比べていわゆる水平型であるので、
耐震上有利な構造となつている。
In addition, the present invention equipment adopts the horizontal annular container 1, which is a so-called horizontal type as compared with the conventional upright type.
It has a structure that is advantageous in terms of earthquake resistance.

〔発明の効果〕〔The invention's effect〕

以上説明したように、本発明の核燃料連続溶解装置の本
体構造によれば、移動する核燃料装荷かごの吊下げ板の
環状容器及び上蓋との取合せ部をシール化したので、駆
動部が発揮性の腐食性処理溶液の雰囲気に接するのを確
実に防止でき、かつ、環状容器の内外間のシールを2重
化したので、腐食性ガスの容器外への漏洩を防止するこ
とができ、安全性及びメンテナンスに優れた核燃料連続
溶解装置の本体構造を提供できるという優れた効果を有
する。
As described above, according to the structure of the main body of the nuclear fuel continuous melting apparatus of the present invention, the assembly of the hanging plate of the moving nuclear fuel loading basket with the annular container and the upper lid is sealed, so that the drive unit is It is possible to reliably prevent contact with the atmosphere of the corrosive treatment solution, and because the seal between the inside and outside of the annular container is doubled, it is possible to prevent leakage of corrosive gas to the outside of the container, and safety and It has an excellent effect that the main body structure of the nuclear fuel continuous melting apparatus excellent in maintenance can be provided.

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

第1図は本発明に係る核燃料連続溶解処理装置の一実施
例を示す全体構成図、第2図は第1図の装置の本体部の
要部拡大断面図、第3図は第1図の装置の本体部の要部
拡大斜視図である。 1……環状容器、2……燃料装荷かご、3……溶解液、
5……上蓋、9……吊上げ装置、10……取出扉、14……
燃料装荷かご吊下げ板、16,17,18……水シール、19……
水補給用配管。
FIG. 1 is an overall configuration diagram showing an embodiment of a nuclear fuel continuous dissolution treatment apparatus according to the present invention, FIG. 2 is an enlarged cross-sectional view of an essential part of a main body of the apparatus of FIG. 1, and FIG. 3 is of FIG. It is a principal part expansion perspective view of the main-body part of an apparatus. 1 ... Annular container, 2 ... Fuel loading basket, 3 ... Dissolved liquid,
5 ... Top lid, 9 ... Lifting device, 10 ... Extraction door, 14 ...
Fuel loading basket suspension plate, 16,17,18 …… Water seal, 19 ……
Water supply piping.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】腐食性を有する溶解処理液を保持し、上部
に上蓋を備える水平式環状容器の内部に、ローラにより
駆動支持された環状壁状の吊下げ板に複数個の核燃料装
荷かごを吊下げて配置するとともに、前記核燃料を装荷
したかごの一定高さを前記溶解処理液に浸漬しつつ、前
記吊下げ板の円環状の移動により前記かごを順次一方向
に移動させて核燃料を溶解する核燃料連続溶解装置の本
体構造において、前記吊下げ板の下部と前記環状容器と
の間、及び、前記吊下げ板の上部と前記上蓋との間のそ
れぞれに、気密性を保持して前記吊下げ板が移動可能な
第1及び第2の水シールが設けられているとともに、前
記環状容器の内周側及び外周側の前記上蓋との接触部に
は、前記環状容器側に凹部を、かつ前記上蓋側に前記凹
部に嵌合する凸部を設け、前記内周側及び外周側のそれ
ぞれの凹凸部に、気密性を維持する第3及び第4の水シ
ールが設けられ、かつ、前記環状容器の上部を塞ぐ上蓋
を一体構造にして、前記環状容器と前記上蓋とのボルト
締付固定部を、前記第4の水シールより外周側に設けた
ことを特徴とする核燃料連続溶解装置の本体構造。
1. A plurality of nuclear fuel loading baskets are mounted on an annular wall-shaped hanging plate which is driven and supported by rollers inside a horizontal annular container which holds a corrosive dissolution treatment liquid and has an upper lid on the upper part thereof. While suspending and arranging, while immersing a certain height of the car loaded with the nuclear fuel in the dissolution treatment liquid, the annular movement of the suspension plate sequentially moves the car in one direction to dissolve the nuclear fuel. In the main body structure of the nuclear fuel continuous melting apparatus, the suspension is performed while maintaining airtightness between the lower portion of the suspension plate and the annular container and between the upper portion of the suspension plate and the upper lid. The first and second water seals in which the lower plate is movable are provided, and a contact portion with the upper lid on the inner peripheral side and the outer peripheral side of the annular container has a concave portion on the annular container side, and A convex portion that fits into the concave portion on the upper lid side The third and fourth water seals that maintain airtightness are provided on the respective concave and convex portions on the inner peripheral side and the outer peripheral side, and the upper lid that closes the upper portion of the annular container is integrally structured, A main body structure of a nuclear fuel continuous melting apparatus, characterized in that a bolted fixing portion between the annular container and the upper lid is provided on the outer peripheral side of the fourth water seal.
JP22078786A 1986-09-18 1986-09-18 Main structure of continuous reactor for nuclear fuel Expired - Fee Related JPH07122680B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP22078786A JPH07122680B2 (en) 1986-09-18 1986-09-18 Main structure of continuous reactor for nuclear fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP22078786A JPH07122680B2 (en) 1986-09-18 1986-09-18 Main structure of continuous reactor for nuclear fuel

Publications (2)

Publication Number Publication Date
JPS6375596A JPS6375596A (en) 1988-04-05
JPH07122680B2 true JPH07122680B2 (en) 1995-12-25

Family

ID=16756560

Family Applications (1)

Application Number Title Priority Date Filing Date
JP22078786A Expired - Fee Related JPH07122680B2 (en) 1986-09-18 1986-09-18 Main structure of continuous reactor for nuclear fuel

Country Status (1)

Country Link
JP (1) JPH07122680B2 (en)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
JPS6375596A (en) 1988-04-05

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