JPS6188190A - Elevator of transport vessel for spent nuclear fuel - Google Patents

Elevator of transport vessel for spent nuclear fuel

Info

Publication number
JPS6188190A
JPS6188190A JP59209650A JP20965084A JPS6188190A JP S6188190 A JPS6188190 A JP S6188190A JP 59209650 A JP59209650 A JP 59209650A JP 20965084 A JP20965084 A JP 20965084A JP S6188190 A JPS6188190 A JP S6188190A
Authority
JP
Japan
Prior art keywords
cask
pool
nuclear fuel
case
spent nuclear
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
JP59209650A
Other languages
Japanese (ja)
Inventor
大角 昭夫
冨田 文昭
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries 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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP59209650A priority Critical patent/JPS6188190A/en
Publication of JPS6188190A publication Critical patent/JPS6188190A/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

Landscapes

  • Types And Forms Of Lifts (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】 (腫業上の利用分野) 本発明は使用済核燃料用輸送容器の昇降装置の改良に関
するものである。
DETAILED DESCRIPTION OF THE INVENTION (Field of medical application) The present invention relates to an improvement in a lifting device for a spent nuclear fuel transport container.

(従来の技術) 原子力施設等において使用済核燃料を使用済核燃料輸送
答器(以下キャスクと呼ぶ)に出し入れする場合、その
作業を作業者の被曝低減及び燃料の発熱除去等のために
、水中で行なうのが一般的である。一方、キャスクの外
面には、収納する使用済核燃料の発熱を放散するために
、複雑な形状のフィンが取シ付けられている場合が多い
が、このフィンがプール水中の放射性物質により汚染さ
れるのを防止するためにこれまでに種々の対策がとられ
ている。
(Prior technology) When transferring spent nuclear fuel to and from spent nuclear fuel transport vessels (hereinafter referred to as casks) at nuclear facilities, etc., the work is carried out underwater to reduce radiation exposure to workers and remove heat generated from the fuel. It is common to do so. On the other hand, complex-shaped fins are often attached to the outside of the cask in order to dissipate the heat generated by the spent nuclear fuel stored therein, but these fins can become contaminated by radioactive materials in the pool water. Various measures have been taken to prevent this.

その対策を第8図によ勺説明する。まずキャスク(1)
をプール(9)に入れる前に、キャスク(1)のフィン
部を円筒形状のバギング装置で被覆する。このバギング
装置には、金属性のもへ(3)参照)、フレキシブルな
もの((4)参照涜があり、同バギング装置とキャスク
(1)との接続部分をシールし、金属性のバギング装置
(3)の場合は、このバギング装置(3)とキャスク(
1)との間(5)に清水を充填した後、天井クレーンα
αによりキャスク(1)をプール(9)の水中に吊り降
ろしてプール(9)の床に着床させる。またフレキジノ
ルなバギング装置(4)の場合は、天井クレーン(10
)によりキャスク(1)をプール(9)の水中に吊シ降
ろしつつ清水を充填した後にプール(9)の床に着床さ
せる。この場合、プール(9)はキャスク(1)から燃
料を取シ出しても十分に遮蔽できる水深があり、クレー
ン(10)のフックがプール(9)の水中に入らないよ
うにその水深に応じた水中吊具(7)が庚用される。
The countermeasures will be explained in detail with reference to FIG. First, the cask (1)
Before being placed in the pool (9), the fins of the cask (1) are covered with a cylindrical bagging device. There are two types of this bagging device: metallic ones (see (3)) and flexible ones (see (4)). In the case of (3), this bagging device (3) and the cask (
After filling the space between (1) and (5) with fresh water, the overhead crane α
The cask (1) is lowered into the water of the pool (9) by α and placed on the floor of the pool (9). In addition, in the case of a flexible bagging device (4), an overhead crane (10
), the cask (1) is lowered into the water of the pool (9), filled with fresh water, and then placed on the floor of the pool (9). In this case, the pool (9) is deep enough to be shielded even if the fuel is removed from the cask (1), and the hook of the crane (10) must be adjusted according to the water depth to prevent it from entering the water in the pool (9). The underwater hanging device (7) is used.

またキャスク(1)の蓋(2)を取ジ伺けているボルト
が予め取ジ外されており、キャスク(1)がプール(9
)の床10着床して、キャスク(1)から吊具(6)が
外ちれると、鋪(2)のみが吊具(6)に取り付けられ
た鎖(8)等により吊り上げられる。つ1シ蓋(2)の
みが水中でキャスク(1)から取り外される。この蓋(
2)は一旦、プール(9)外へ取ジ出されて、表面の汚
染が基準値以内になるよりに除染さ?した後、プール(
9)の近くの雉のられた場所に仮置される。次いで専用
の燃料取扱クレーンによりキャスク(11の内部の使用
済核燃料が取り出されたシ、キャスク(1)の内部に使
用済核燃料が入れられたりする。燃料の出し入れが終る
と、前記天井クレーン(101と水中吊具(7)とを用
いてプール(9)外に仮置されている蓋(2)が吊シ上
けられ、プール(9)の水中のキャスク(1)に装着さ
れ、キャスク(1)本体に吊具(6)が係合さnて、キ
ャスク(1)が水中から吊り上けられる。このとき、プ
ール(9)上ではキャスク(1)の露出表面及びバギン
グ材の表面が水洗いされ、キャスク除染場に運ばれ、こ
こでバギング装置が取り外されて、キャスク(1)の表
面が除染される。
In addition, the bolt that allows the lid (2) of the cask (1) to be removed has been removed in advance, and the cask (1) is attached to the pool (9).
) When the person lands on the floor 10 of the cask (1) and the hanging tool (6) is detached from the cask (1), only the plow (2) is lifted up by the chain (8) etc. attached to the lifting tool (6). Only one lid (2) is removed from the cask (1) underwater. This lid (
2) is once taken out of the pool (9) and decontaminated until the surface contamination is within the standard value? After that, the pool (
9) It will be temporarily placed in the place where the pheasant was covered. Next, the spent nuclear fuel inside the cask (11) is taken out by a dedicated fuel handling crane, and the spent nuclear fuel is put into the inside of the cask (1).Once the fuel has been taken out and taken out, the overhead crane (101) The lid (2) temporarily placed outside the pool (9) is hoisted up using the and underwater lifting equipment (7), attached to the cask (1) underwater in the pool (9), and the cask ( 1) The lifting tool (6) is engaged with the body and the cask (1) is lifted out of the water.At this time, the exposed surface of the cask (1) and the surface of the bagging material are on the pool (9). It is washed with water and transported to a cask decontamination site, where the bagging equipment is removed and the surface of the cask (1) is decontaminated.

nI記使用済核燃料輸送容器の昇降装置では、(1)キ
ャスク(11の取扱いに長尺の水中吊具(力を必要とす
るため、取扱いが不便であった。(Illキャスク(1
)のバギングされている個所は汚染しないが、キャスク
(1)の露出部及びバギング装置の表面は、プール水中
の放射性物質により汚染される。このため、プール上で
水洗いを行うが、これでは完全な除染が困難であり、除
染場へ移動して、拭き取り等により完全に除染するが、
このとき、施設床等へ汚染を拡大する恐れがあった。ま
たキャスク(1)及びバギング装置(31(4)は、繰
り返し便用するものでろるから、一旦汚染した部分を完
全に除染する必要がちり、この除染作業に多くの時間と
労力を必要としていた。(1)バギング装置は、かなシ
大きなものでちゃ、除染時の数カ扱いが不便であった。
In the elevating device for the spent nuclear fuel transport container described in I, (1) It was inconvenient to handle the cask (11) because it required a long underwater hanging device (force) to handle the cask (11).
) will not be contaminated, but the exposed parts of the cask (1) and the surface of the bagging device will be contaminated by radioactive materials in the pool water. For this reason, washing is done in the pool, but it is difficult to completely decontaminate the water, so we move to a decontamination site and completely decontaminate by wiping, etc.
At this time, there was a risk of contamination spreading to the facility floors. In addition, since the cask (1) and the bagging device (31 (4)) are used repeatedly, it is necessary to completely decontaminate the contaminated area, and this decontamination work requires a lot of time and effort. (1) The bagging equipment was quite large, making it inconvenient to handle multiple units during decontamination.

側外形形状の異なる各種キャスクに対応して各種のバギ
ング装置を必要としておシ、そのため、バギング装置の
保管に広い場所を必要として、不経済であった。
Various bagging devices are required to accommodate various types of casks having different side external shapes, and therefore, a large space is required to store the bagging devices, which is uneconomical.

(問題点を)π決するだめの手段) 本発明は前記の問題点に対処するもので、プールの壁に
沿う昇降が可Hになケージと、同ケージ内に立設した水
密的のケースと、同ケースの上部と同ケース内に収納し
た使用済核燃料用輸送容器の上部との間の隙+i41を
水密的に閉じるシールカバーとを有し、同ンールカバー
の内周縁側を花弁状に分割するとともtて同各分割片の
隣接縁部を防水ファスナーにより開閉可能に連結し、同
各分割片の内周矛〜貞側中央部pcひだ状の重複部?形
成するとともに同重復部の両側縁を防水ファスナにより
開閉可能に連結したことを特徴とする使用済核燃料用輸
送容器の昇降装置に隙ジ、その目的とする処は、プール
水中で核燃料のキャスクに対する取り出しまたは装荷を
行うときに、(1)キャスクの外表面の汚染を防止でき
る。(n)プール外に取出すプール水により汚染された
部分がキャスクの上部のみの表面積の極めて少ない部分
なって、施設床等への汚染拡大を防止でき且つキャスク
の除染作業を容易に行うことができる。(11)ケース
上部を花弁状に開閉できて、ケースに対するキャスクの
収納作業を容易に行うことができる。頂ケース上部のシ
ールカバーに内径寸法を調整できるひだ状の重複部を持
っており、外径の異なる各種のキャスクに対応できて、
これまでのようにキャスクの種類に応じてバギング装置
を取り替る必要がない。(■キャスクの外表面を防染す
るためのケースを立設したケージを昇降塾せるようにし
ており、これまでのように長尺の水中吊具を必要としな
くて、昇降作業を容易に行うことができる改良された使
用済核燃料用輸送容器の昇降装置を供する点にある。
(Means for resolving the problem) The present invention addresses the above-mentioned problems by providing a cage that can be raised and lowered along the wall of the pool, and a watertight case installed vertically within the cage. , a seal cover that watertightly closes the gap +i41 between the upper part of the case and the upper part of the spent nuclear fuel transport container stored in the case, and the inner peripheral edge side of the container cover is divided into petal shapes. Adjacent edges of each of the divided pieces are connected to each other so that they can be opened and closed using a waterproof zipper, and an overlapping part of the inner periphery of each divided piece to the central part of the outer side is folded. A gap is formed in the elevating device for the spent nuclear fuel transport container, which is characterized by forming and opening/closingly connecting both sides of the overlapping part with waterproof fasteners. (1) Contamination of the outer surface of the cask can be prevented when unloading or loading. (n) The area contaminated by the pool water taken out of the pool is only the upper part of the cask, which has an extremely small surface area, which prevents the spread of contamination to the facility floor, etc., and makes it easier to decontaminate the cask. can. (11) The upper part of the case can be opened and closed like a petal, making it easy to store the cask in the case. The seal cover at the top of the top case has a pleated overlapped part that allows adjustment of the inner diameter dimension, making it compatible with various casks with different outer diameters.
There is no need to replace the bagging device depending on the type of cask, unlike in the past. (■The cage, which has a case installed to protect the outer surface of the cask, can be lifted up and down, making lifting and lowering easier without the need for long underwater hanging equipment as in the past. An object of the present invention is to provide an improved device for lifting and lowering a spent nuclear fuel transport container.

(実施列) 次に本発明の使用済核燃料用輸送容器の昇降装置を第1
図乃至第7図に示す一実施例により説明すると、αυが
内部に水を満たしたプールであり、内壁面にステンレス
のライニングが施こされている。またα2がプールaυ
の水中をガイドレールに沿って上下方向に移動可能なケ
ージ、α国が同ケージ(121をプールαυの水中に昇
降させるための昇降駆動装置、Q=1)が使用済核燃料
を輸送するための使用済核燃料輸送容器(以下キャスク
と呼ぶ)、(15)が昇降ケージtlzの内部に立設し
たキャスク収納用ケースでめ9、底板をもつ筒形に形成
されている。また同ケース(19の上部には、内周縁側
を花弁状に分割したシールカバーueが水密的に取付け
られている。同シールカバーa0は、布にゴム2イニン
グを施す等して防水性をもたせたフレキシブルな材料で
作られてお)、上述のように内周縁側を花弁状に分割し
て形成した各分割片の隣接縁部には、防水ファスナー(
17)が取付けられている。そのだめ、防水ファスナー
(17)を開くと、シールカバーQ6)が開花したよう
に広がり(第5図参照)、防水ファスナー07)を閉じ
ると、シールカバー(leが花弁を閉じたよりに截頭円
錐状になる(第6図参照)。またこのシールカバーu6
)の各分割片の内周縁側中央部には、ひだ状の重複部猪
が設けられている。このひだ状の重複部Oaは、防水フ
ァスナー(19により開閉が可能で、この防水ファスナ
ー(11を閉じると、ひだ状の重複部QFjが折り重な
多、内部にとじ込められて、内径がさらに細くなる(第
7図参照)。
(Implementation row) Next, the device for lifting and lowering the spent nuclear fuel transport container of the present invention is installed in the first row.
To explain with an embodiment shown in FIGS. 7 to 7, αυ is a pool filled with water, and the inner wall surface is lined with stainless steel. Also, α2 is the pool aυ
A cage that can be moved vertically along guide rails in the water of Pool αυ, and Country α has developed a cage (lift drive device for raising and lowering 121 into the water of Pool αυ, Q = 1) for transporting spent nuclear fuel. A spent nuclear fuel transport container (hereinafter referred to as a cask) (15) is a cask storage case erected inside the elevator cage tlz, and is formed into a cylindrical shape with an eye 9 and a bottom plate. In addition, a seal cover ue whose inner peripheral edge is divided into petal shapes is attached to the upper part of the case (19) in a watertight manner. The inner peripheral edge is divided into petal-shaped pieces as described above, and the adjacent edges of each segment are equipped with waterproof zippers (
17) is installed. Instead, when the waterproof zipper (17) is opened, the seal cover Q6) spreads out like a flower (see Figure 5), and when the waterproof zipper 07) is closed, the seal cover (le is shaped like a truncated cone with closed petals). (See Figure 6).Also, this seal cover u6
) A pleated overlapping portion is provided at the center portion on the inner peripheral edge side of each divided piece. This pleated overlapping portion Oa can be opened and closed by a waterproof zipper (19), and when this waterproof zipper (11) is closed, the pleated overlapping portion QFj is folded and confined inside, further increasing the inner diameter. It becomes thinner (see Figure 7).

そのため、この防水ファスナーHにより閉じられる部分
の数を増減することにより截頭円錐状としたシールカバ
ー00の内径寸法を段階的に調整することができる。こ
れにより外径寸法の異なる種々のキャスクIに対しても
同一のシールカバーueによジ、ケースQ51の上部と
キャスク041の上部との間の隙間を水密的に7−ルで
きる。また(4)がキャスクQ4)の表面とケース本体
<15)及び7−ルカバー16jとにより形成される空
間に清水を供給するためのフレキシブルホースで、同フ
レキシブルホースI20)より前記空間へ清水を供給し
て充満6せる。
Therefore, by increasing or decreasing the number of parts closed by the waterproof fastener H, the inner diameter of the truncated conical seal cover 00 can be adjusted stepwise. As a result, the gap between the upper part of the case Q51 and the upper part of the cask 041 can be sealed watertightly even for various casks I having different outer diameters by using the same seal cover ue. In addition, (4) is a flexible hose for supplying fresh water to the space formed by the surface of the cask Q4), the case body <15), and the 7-rule cover 16j, and the flexible hose I20) supplies fresh water to the space. and fill it up to 6.

(作 用) 次に11J記キヤスク(使用済核燃料輸送容器)の作用
を説明する。まずキャスク側の受は取シ準備状態を説明
すると、昇降ケージα2及びケースu9がプール0υの
最上昇位置に停止し、シールカバー(IQの分割片の隣
接縁部に設けられた防水ファスナー卸が開かれて、シー
ルカバー(16)の各分割片が開花した拡開状力で待機
している。次いでキャスクIが砲設内の天井クレーン等
(図示せず)により吊り上げられ、昇降ケージα2内に
設けられたケース本体(l■内に吊り降ろされて、収納
される。この状態は第2図に示す通りで、キャスクα旬
の上部がケース(15)から突き出ている。次いでキャ
スク側の表面を防染するために、シールカバー(1G)
に取付けた防水ファスナーα7)ヲ閉じる。次いでキャ
スク側の外周とシールカバー(16)の内周縁内径とが
ほぼ等しくなるよりtζシール刀バーaυに設げノζひ
だ状の重複部(1aを折り重ね、これを内部にとじ込め
るようにして防水ファスナー(11の適当数を閉じる。
(Function) Next, the function of the cask (spent nuclear fuel transport container) described in 11J will be explained. First, to explain the preparation state for removing the receiver on the cask side, the elevator cage α2 and the case u9 stop at the highest position of the pool 0υ, and the seal cover (waterproof fastener outlet provided on the adjacent edge of the divided piece of IQ) is opened. The seal cover (16) is opened and each segment of the seal cover (16) is waiting in an expanded state.Then, the cask I is lifted up by an overhead crane or the like (not shown) in the gun installation and placed in the elevator cage α2. The case body (l) provided in Seal cover (1G) to protect the surface
Close the waterproof zipper α7) attached to the Next, until the outer periphery of the cask side and the inner diameter of the inner periphery of the seal cover (16) are approximately equal, a folded overlapping part (1a) is provided on the seal bar aυ so that it can be folded over and kept inside. Close the appropriate number of waterproof zippers (11).

キャスク■の外径が細い場合は、多い数の防水ファスナ
ーα■を閉じ、逆にキャスク(14)の外径が太い場合
は、少い数の防水ファスナーα→を閉じるようにすれば
よい。なおこの部分の水密性は、図示していないが、キ
ャスクu4の外周に予め弾性体のパツキンを巻いたシ、
防水ファスナー(1Gを閉じたシールカバー161の上
から弾性体のバンドを巻いたり、テープを貼シ付けたシ
して、確保する。次いでフレキシブルホース四よシ清水
を供給しキャスク(1□0の表面とケースt15)及び
シールカバー(10との間に形成された空間に清水を満
す。以上の作業終了後、昇降駆動装置叫により、キャス
ク(14)を収納したケースα9を昇降ケージa2と共
にプールQl)の最深部まで吊り降す。この後は、従来
と同様に燃料取扱クレーン(図示せず)を用いてキャス
ク側に対する使用済核燃料の取シ出しまたは装荷を行う
。使用済核燃料の取9出しまたは装荷が児了すれは、逆
の順序で作業を行えばよい。
If the outer diameter of the cask (14) is small, a large number of waterproof fasteners α■ may be closed, and if the outer diameter of the cask (14) is large, a small number of waterproof fasteners α→ may be closed. Although not shown, the watertightness of this part can be determined by wrapping an elastic packing around the outer periphery of the cask U4 in advance.
Secure the waterproof zipper (1G) by wrapping an elastic band or pasting tape over the closed seal cover 161. Next, supply fresh water with a flexible hose and close the cask (1□0) The space formed between the surface and the case t15) and the seal cover (10) is filled with clean water. After the above work is completed, the elevating drive device shouts to move the case α9 containing the cask (14) together with the elevating cage a2. It is lowered to the deepest part of the pool (Ql).After this, the spent nuclear fuel is removed or loaded into the cask side using a fuel handling crane (not shown) in the same way as in the past. If loading or unloading is completed, you can perform the work in the reverse order.

(発明の効果) 本発明の使用済核燃料輸送容器の昇降装置は6’tJ記
のようにプールの壁に沿う昇降が可能なケージと、同ケ
ージ内に立設した水密性のケースと、同ケースの上部と
同ケース内に収納した使用所俵燃料用輸送容器の上部と
の間の隙間を水密的に閉じる/−ルカバーとを有し、同
7−ルカバーの内周縁ft1ll f花弁状に分割する
とともに同各分λI]片の隣接縁部を防水ファスナーに
よυ開閉可能に連結し、同各分ル1片の内周縁側中央部
にひだ状の重複部を形成するとともに同重複部の両側縁
を防水ファスナにより)ji’l閉可能に連結しており
、+jiJ記の作用が行われるので、次の効果ケ達成で
きる。即ち、プール水中で使用済核燃料のキャスクに対
する取り出しまたは装荷を行うときに、(I)キャスク
の外表面がプール水中の放射性物質により汚染されるの
を防止でさる。(It)ヤヤスク収納柑ケースの上部に
水密的に取付けたシールカバーの内周縁側を花弁のよう
(/(複数に分割し且つ同各分割片の隣接線部に防水フ
ァスナーを取付けており、キャスクのケースに対する出
し入れ及びシールカバーに行9ことができる。(Ifl
)前記シールカバーの各分割片の内周縁9111中矢部
にひだ状の重複部を設け、その両側縁に重・腹部の開閉
可能な防水ファスナーを設けてヒシ、シールカバーの内
径を段階的に調整できる。
(Effects of the Invention) The device for lifting and lowering the spent nuclear fuel transport container of the present invention includes a cage that can be moved up and down along the wall of the pool, as shown in section 6'tJ, and a watertight case installed vertically within the cage. It has a cover that watertightly closes the gap between the upper part of the case and the upper part of the transport container for fuel bales stored in the same case, and the inner peripheral edge of the cover is divided into petal shapes. At the same time, the adjacent edges of each of the same pieces are connected so that they can be opened and closed by a waterproof zipper, and a pleated overlapping part is formed at the center of the inner peripheral edge of each piece of the same piece, and the overlapped part is Both side edges are connected so that they can be closed by waterproof fasteners, and the following effects are achieved, so that the following effects can be achieved. That is, when spent nuclear fuel is taken out or loaded into the cask in the pool water, (I) it is possible to prevent the outer surface of the cask from being contaminated by radioactive substances in the pool water; (It) The inner edge of the seal cover, which is watertightly attached to the top of the Yayask storage case, is divided into multiple pieces like flower petals (/(), and a waterproof zipper is attached to the adjacent line of each divided piece. Line 9 can be inserted into and taken out of the case and the seal cover. (If
) A fold-like overlapping part is provided at the middle arrow part of the inner peripheral edge 9111 of each divided piece of the seal cover, and waterproof zippers that can be opened and closed are provided on both sides of the overlap part to adjust the inner diameter of the caltrop and seal cover in stages. can.

従って外径の異なる各種のキャスクに対し同一のシール
カバーで対応できて、これまでのように7−ルカパーを
キャスクの種類に合せて何種類も用意する必要がない。
Therefore, the same seal cover can be used for various types of casks with different outer diameters, and there is no need to prepare multiple types of 7-capers to match the types of casks, as was the case in the past.

■キャスク収納用ケース及びシールカバーは、常にプー
ル壁に沿って昇降する昇降ケージに設けられておシ、こ
れまでのように直接プール水と接触したバギング装置を
プール外に取シ出すことがなく、プール外に取出すプー
ル水により汚染され部分がキャスクの上部のみの表面積
の極めて少ない部分になって、施設床等への汚染拡大を
防止でき且つ除染作業を容易に行うことができる。なお
これまでは、バギング装置も再使用するため、除染して
いて、これに多大の労力を要していた。なおキャスクと
ケースとシールカバーとにより形成される空1”i’+
に充満させる清水は、清水に限るものではなく、他の液
体、気体またはゼリー状の半固形状のものでもよく、1
だ多少加圧すれは、万一シール部分が不完全であっても
プール水をこの空間に入り込ませることがない。
■The cask storage case and seal cover are installed in a lifting cage that always moves up and down along the pool wall, eliminating the need to take out the bagging device that came into direct contact with the pool water outside the pool, unlike in the past. The area contaminated by the pool water taken out of the pool is only the upper part of the cask, which has an extremely small surface area, making it possible to prevent the spread of contamination to the facility floor, etc., and to facilitate decontamination work. Until now, the bagging equipment had to be decontaminated in order to be reused, which required a great deal of effort. Note that the air space 1"i'+ formed by the cask, case, and seal cover
The fresh water to be filled is not limited to fresh water, but may be other liquids, gases, or semi-solids such as jelly.
Even if the seal is imperfect, pool water will not be able to enter this space by applying some pressure.

以上本発明を実施例について説明したが、勿論本発明は
このような実施例にだけ局限されるものではなく、本発
明の精神を逸脱しない範囲内で種々の設計の改変を施し
うるものである。
Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to such embodiments, and that various design modifications can be made without departing from the spirit of the present invention. .

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

第1図は本発明に係る使用済核燃料輸送容器の昇降装置
の一実施例のプール最上部におけるケースへのキャスク
受は入れ直後の状態を示す平面図、第2図はそのときの
側面図、第3図はプール最深部におけるキャスクへの核
燃料出し入れ時の状態を示す平面図、第4図はそのとき
の側面図、第5図はケースカフe−の拡開状態を示す斜
視図、第6図はケースカバーの分割片を閉じたときの斜
視図、第7図はケースカバーの分割片及び重複部の一部
を閉じたときの斜視図、第8図は従来の使用済核燃料用
輸送容器の昇降装置を示す11111面図である。 Uυ・・・プール      aり・・・ケージ0(イ
)・・・使用済核燃料容器 α9・・・ケース0e・・
・シールカメ− 0′?)・・・シールカバー(16)の分割片の隣接縁
部を開閉可能に連結する防水ファスナー α帽・・重複部 α岨・・重複部Uの両側縁を開閉可能に連結する防水フ
ァスナー。 仮代理人 弁理士 岡 本 重 文 外3名 第1図 気3閉 @5に 第6図
FIG. 1 is a plan view showing a state immediately after the cask receiver is inserted into the case at the top of the pool of an embodiment of the device for lifting and lowering a spent nuclear fuel transport container according to the present invention, and FIG. 2 is a side view at that time. Fig. 3 is a plan view showing the state when nuclear fuel is taken in and out of the cask at the deepest part of the pool, Fig. 4 is a side view at that time, Fig. 5 is a perspective view showing the expanded state of case cuff e-, Fig. 6 7 is a perspective view of the case cover when the divided pieces are closed, FIG. 7 is a perspective view of the case cover when the divided pieces and part of the overlapping part are closed, and FIG. 8 is a perspective view of a conventional spent nuclear fuel transport container. It is a 11111 side view showing the elevating device. Uυ...Pool ari...Cage 0 (A)...Spent nuclear fuel container α9...Case 0e...
・Seal turtle - 0'? )...Waterproof fastener α that connects the adjacent edges of the divided pieces of the seal cover (16) in an openable and closable manner.Overlapping portion α-cap: A waterproof fastener that connects both sides of the overlapping portion U in an openable and closable manner. Temporary agent Patent attorney Shige Okamoto 3 people outside of the text 1st image 3rd @ 5th and 6th figure

Claims (1)

【特許請求の範囲】[Claims] プールの壁に沿う昇降が可能なケージと、同ケージ内に
立設した水密性のケースと、同ケースの上部と同ケース
内に収納した使用済核燃料用輸送容器の上部との間の隙
間を水密的に閉じるシールカバーとを有し、同シールカ
バーの内周縁側を花弁状に分割するとともに同各分割片
の隣接縁部を防水ファスナーにより開閉可能に連結し、
同各分割片の内周縁側中央部にひだ状の重複部を形成す
るとともに同重複部の両側縁を防水ファスナにより開閉
可能に連結したことを特徴とする使用済核燃料用輸送容
器の昇降装置。
The gap between the cage that can be raised and lowered along the pool wall, the watertight case installed vertically inside the cage, and the top of the case and the top of the spent nuclear fuel transport container stored in the case is and a seal cover that closes in a watertight manner, the inner peripheral edge of the seal cover is divided into petal shapes, and the adjacent edges of each divided piece are connected so as to be openable and closable with a waterproof zipper,
A device for lifting and lowering a spent nuclear fuel transport container, characterized in that a pleated overlapping portion is formed at the center of the inner peripheral edge of each divided piece, and both side edges of the overlapping portion are openably and closably connected by a waterproof fastener.
JP59209650A 1984-10-08 1984-10-08 Elevator of transport vessel for spent nuclear fuel Pending JPS6188190A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59209650A JPS6188190A (en) 1984-10-08 1984-10-08 Elevator of transport vessel for spent nuclear fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59209650A JPS6188190A (en) 1984-10-08 1984-10-08 Elevator of transport vessel for spent nuclear fuel

Publications (1)

Publication Number Publication Date
JPS6188190A true JPS6188190A (en) 1986-05-06

Family

ID=16576311

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59209650A Pending JPS6188190A (en) 1984-10-08 1984-10-08 Elevator of transport vessel for spent nuclear fuel

Country Status (1)

Country Link
JP (1) JPS6188190A (en)

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