JPH07325191A - Transportation stage for wet transportation cask - Google Patents
Transportation stage for wet transportation caskInfo
- Publication number
- JPH07325191A JPH07325191A JP6118657A JP11865794A JPH07325191A JP H07325191 A JPH07325191 A JP H07325191A JP 6118657 A JP6118657 A JP 6118657A JP 11865794 A JP11865794 A JP 11865794A JP H07325191 A JPH07325191 A JP H07325191A
- Authority
- JP
- Japan
- Prior art keywords
- transportation
- wet
- pair
- container
- cask
- 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.)
- Withdrawn
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Filling Or Discharging Of Gas Storage Vessels (AREA)
Abstract
Description
【0001】[0001]
【産業上の利用分野】本発明は、原子力発電所等から発
生する使用済核燃料を収容した湿式輸送容器を所定の保
管場所ないしは設備に輸送する際に、その湿式輸送容器
を輸送用の車両等に固縛・支持する輸送架台に関するも
のである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a vehicle for transporting a wet transportation container containing spent nuclear fuel generated from a nuclear power plant or the like to a predetermined storage place or facility. It relates to a transportation platform that is secured and supported on.
【0002】[0002]
【従来の技術】原子力発電所等から発生する使用済核燃
料は、放射性核種の自己崩壊や自発核***により、自身
より大量の崩壊熱を発生するため、これら使用済核燃料
を収容して輸送する容器には、その輸送容器そのものの
内部に水を入れることや、外周面に放熱用のフィン等を
設けるなどの様々な工夫がなされている。2. Description of the Related Art Spent nuclear fuel generated from a nuclear power plant or the like generates a large amount of decay heat from itself due to self-destruction or spontaneous fission of radionuclides. Various measures have been taken, such as putting water inside the transportation container itself and providing fins for heat dissipation on the outer peripheral surface.
【0003】それらの内の代表的な湿式輸送容器の外郭
形状を、〔図2〕の (d)図に示す。この湿式輸送容器
(C))は、筒状の密封圧力容器に形成され、その胴部外周
面に多数の放熱フィン(F) を設けると共に、両端部に2
対のトラニオン(T) を設けている。そして、この湿式輸
送容器(C))内には、使用済の核燃料ピンの集合体と、こ
の集合体を保持するためのバスケットが収容され、ま
た、そのバスケット内には水が充填される。The outer shape of a typical wet transport container among them is shown in FIG. 2 (d). This wet shipping container
(C)) is formed in a cylindrical sealed pressure vessel, and a large number of heat radiating fins (F) are provided on the outer peripheral surface of the body portion, and 2
It has a pair of trunnions (T). Then, in the wet transport container (C), an assembly of spent nuclear fuel pins and a basket for holding the assembly are housed, and the basket is filled with water.
【0004】また従来では、この種の湿式輸送容器(C)
を、所定保管場所ないしは設備に輸送する際に必要とな
る輸送架台は、その正面図および側面図である同 (a)図
および (b)図に示すように、平盤状の基台(11)と、この
基台(11)の前後両端部上に立設され、その上端部に左右
で対のクランプ(13)を設けた前後の支持部(12)とで構成
されたものが、一般的に採用されている。そして、上記
湿式輸送容器(C) は、同 (c)図に示すように、両端部の
トラニオン(T) を、この輸送架台の前後の支持部(12)の
対のクランプ(13)で把持され、該輸送架台を介して、こ
こでは図示を省略した輸送用車両の搭載部に水平に固縛
・支持される。Further, conventionally, this type of wet transportation container (C) has been used.
As shown in Figures (a) and (b) of the front and side views, the transportation platform required for transporting the ) And a support part (12) which is erected on both front and rear ends of this base (11) and has a pair of left and right clamps (13) provided on the upper end of the base (11). Has been adopted as Then, the wet transport container (C) holds the trunnions (T) at both ends with the pair of clamps (13) of the front and rear support parts (12) of the transport base, as shown in FIG. Then, it is horizontally secured and supported via the transportation base to a mounting portion of a transportation vehicle (not shown here).
【0005】[0005]
【発明が解決しようとする課題】しかし、前記従来の輸
送架台では、湿式輸送容器を水平に支持するため、その
湿式輸送容器内に収容された使用済の燃料ピンの集合体
とバスケットとの間にある水が、該湿式輸送容器の軸方
向には効率的に流れないため、径方向の対流伝熱によっ
てのみ崩壊熱が伝わることになり、結果的に支持した湿
式輸送容器の内部温度が高くなり、それに伴い内圧が高
くなると言う問題が発生していた。すなわち、前記従来
の輸送架台は、湿式輸送容器を確実に固縛・支持して輸
送中での落下等の事故を防止することを主目的とし、そ
の湿式輸送容器の除熱性能の促進については特に考慮し
て設計されていなかった。However, in the above-described conventional transportation stand, since the wet transportation container is supported horizontally, the space between the assembly of the spent fuel pins housed in the wet transportation container and the basket. Since the water in the column does not flow efficiently in the axial direction of the wet transport container, the decay heat is transferred only by the radial convective heat transfer, and as a result, the internal temperature of the supported wet transport container is high. Then, there was a problem that the internal pressure was increased accordingly. That is, the above-mentioned conventional transportation cradle has the main purpose of securely securing and supporting the wet transportation container to prevent an accident such as a drop during transportation. It was not specifically designed.
【0006】本発明は、上記従来技術の問題点に対処す
るためのもので、使用済核燃料と共に水を収容した湿式
輸送容器を支持し、輸送用車両の搭載部に確実に固縛で
きてなお、支持した湿式輸送容器に対して、内部に収容
されている水が、使用済核燃料の崩壊熱量に応じて、軸
方向に流動することを促す動き与えて、その除熱機能を
促進させることができ、よって輸送中における湿式輸送
容器の内部温度および内圧の上昇を抑制できる湿式輸送
容器の輸送架台を提供することを目的とする。The present invention addresses the above-mentioned problems of the prior art. It supports a wet transportation container containing water together with spent nuclear fuel, and can be securely fastened to a mounting portion of a transportation vehicle. , To the supported wet transport container, the water contained therein can be moved to promote axial flow according to the amount of decay heat of the spent nuclear fuel, thereby promoting its heat removal function. An object of the present invention is to provide a transportation platform for a wet transportation container, which can suppress an increase in internal temperature and internal pressure of the wet transportation container during transportation.
【0007】[0007]
【課題を解決するための手段】上記の目的を達成するた
めに、本発明は以下の構成とされている。すなわち、本
発明に係る湿式輸送容器の輸送架台は、車両の搭載部に
載置連結される平盤状の基台と、この基台の前後両端部
上に立設され、その上端部に左右で対のクランプを設け
た前後の支持部とを備え、使用済核燃料を水と共に収容
した湿式輸送容器の両端部に設けられた2対のトラニオ
ンを、前記支持部の各クランプで把持し、この湿式輸送
容器を車両の搭載部に固縛して輸送する湿式輸送容器の
輸送架台において、前記前後の支持部の内の少なくとも
一方の支持部に、その支持部自体ないしは上端部の対の
クランプを昇降させるシリンダ装置を設けてなることを
特徴とする。In order to achieve the above object, the present invention has the following constitution. That is, the transportation platform of the wet transport container according to the present invention includes a flat plate-shaped base mounted and connected to a mounting portion of a vehicle, and is erected on both front and rear ends of the base, and the left and right sides are installed at the upper end of the base. And a pair of front and rear supports provided with clamps, and two pairs of trunnions provided at both ends of a wet transportation container containing spent nuclear fuel together with water are held by the clamps of the supports. In a transportation platform for a wet transportation container that transports a wet transportation container by fixing it to a vehicle mounting portion, at least one of the front and rear supporting portions is provided with the supporting portion itself or a pair of upper end clamps. It is characterized in that a cylinder device for raising and lowering is provided.
【0008】[0008]
【作用】本発明の輸送架台では、車両の搭載部に載置連
結される基台の前後両端部上に、その上端部に左右で対
のクランプを設けた前後の支持部を立設しているので、
湿式輸送容器の両端部に設けられた2対のトラニオン
を、前後の支持部の各クランプで把持し、この湿式輸送
容器を車両の搭載部に確実に固縛・支持して輸送するこ
とができる。また、前後の支持部の内の少なくとも一方
の支持部に、その支持部自体ないしは上端部の対のクラ
ンプを昇降させるシリンダ装置を設けているので、輸送
途中において、そのシリンダ装置を作動させて支持した
湿式輸送容器の傾きを変更し、該湿式輸送容器の内部に
収容されている水が、共に収容されている使用済核燃料
の崩壊熱量に応じて、軸方向に流動することを促して、
内部の伝熱性能を高め、これにより該湿式輸送容器の除
熱機能を促進し、輸送中における内部温度および内圧の
上昇を抑制することができる。In the transportation base according to the present invention, front and rear supporting portions having a pair of left and right clamps at the upper end thereof are erected on both front and rear ends of the base mounted and connected to the vehicle mounting portion. Because
The two pairs of trunnions provided at both ends of the wet transportation container can be gripped by the respective clamps of the front and rear supporting portions, and the wet transportation container can be securely bound and supported on the vehicle mounting portion for transportation. . In addition, since at least one of the front and rear supporting parts is provided with a cylinder device for raising and lowering the supporting part itself or a pair of upper end clamps, the cylinder device is operated and supported during transportation. By changing the inclination of the wet transport container, the water contained in the wet transport container is urged to flow in the axial direction in accordance with the decay heat amount of the spent nuclear fuel stored together,
It is possible to enhance the internal heat transfer performance, thereby promoting the heat removal function of the wet transportation container, and suppressing an increase in internal temperature and internal pressure during transportation.
【0009】[0009]
【実施例】以下、本発明の実施例について図面を参照し
て説明する。〔図1〕は、本発明に係る輸送架台の1実
施例の概要構成を示す図面であって、 (a)図は一部を切
欠いて示す正面図、 (b)図は側面図、 (C)図は湿式輸送
容器の支持および作動状態の説明図である。Embodiments of the present invention will be described below with reference to the drawings. [FIG. 1] is a drawing showing a schematic configuration of one embodiment of a transportation platform according to the present invention, in which (a) is a front view with a part cut away, (b) is a side view, (C) ) The figure is an illustration of the support and operating state of the wet transport container.
【0010】〔図1〕の (a)図および (b)図において、
(1) は基台であって、この基台(1)は、長方形平盤状に
形成されると共に、ここでは図示を省略した吊上フック
係合部および車両搭載部への連結固定具を備えてなる。In (a) and (b) of FIG. 1,
(1) is a base, and the base (1) is formed in a rectangular flat plate shape, and a lifting hook engaging portion and a connecting fixture to a vehicle mounting portion (not shown) are attached here. Be prepared.
【0011】(2) は支持部であって、この支持部(2)
は、基台(1) の前後両端部上に立設され、その左右両側
に対の支柱部(2a)を設けると共に、それら対の支柱部(2
a)の下部を平板状の横桁(2b)で連結して1体化させてい
る。また、その対の支柱部(2a)それぞれは、左右で軸状
体を回動自由に把持する対のクランプ(3) を上端部に設
ける一方、外部から油圧の供給を受けて同期作動する昇
降シリンダ(4) を下端部に配設すると共に、その昇降シ
リンダ(4) のラム(4a)下端を基台(1) 上面に接続させて
おり、この構成のもとで、昇降可能に基台(1) 上に立設
されている。また、その前後の支持部(2) の各クランプ
(3) の荷重負荷部となる下部には、把持する軸状体の回
動を円滑にするためのベアリング(3a)を配している。(2) is a support part, and the support part (2)
Are erected on both front and rear ends of the base (1), and a pair of support columns (2a) are provided on both left and right sides of the base (1).
The lower part of a) is connected by a plate-shaped cross girder (2b) to be integrated. In addition, each pair of support columns (2a) is provided with a pair of clamps (3) at the upper end to hold the shaft body freely on the left and right, while raising and lowering in synchronization with the supply of hydraulic pressure from the outside. The cylinder (4) is installed at the lower end, and the lower end of the ram (4a) of the lifting cylinder (4) is connected to the upper surface of the base (1). (1) Standing on top. In addition, each clamp of the support part (2) before and after it
A bearing (3a) for smoothing the rotation of the shaft-like body to be gripped is arranged in the lower part of the load-carrying part of (3).
【0012】上記構成の本実施例の輸送架台では、使用
済核燃料と共に水を収容した湿式輸送容器を、所定保管
場所または設備に輸送する際に、その湿式輸送容器の両
端部のトラニオンを、前後の支持部(2) の左右で対のク
ランプ(3) で把持して、ここでは図示を省略した輸送車
両の搭載部に固縛・支持する。なお、対象の湿式輸送容
器は、〔図2〕の (d)図に示した湿式輸送容器(C) と同
種のもので、その胴部外周面に多数の放熱フィン(F) を
設けると共に、両端部に2対のトラニオン(T) を設けた
筒状の密封圧力容器とされ、その内部には、使用済の核
燃料ピンの集合体と、該集合体を保持するバスケットが
収容され、更に、そのバスケット内に水が充填されてい
る。そして、その両端部の2対のトラニオン(T) が、
〔図1〕の (c)図に示すように、本実施例の輸送架台の
前後の支持部(2) の各クランプ(3) に回動自由に把持さ
れ、これによって輸送車両の搭載部に固縛・支持され
る。In the transportation platform of this embodiment having the above-mentioned structure, when the wet transportation container containing the spent nuclear fuel and water is transported to a predetermined storage place or facility, the trunnions on both ends of the wet transportation container are moved forward and backward. It is gripped by a pair of clamps (3) on the left and right sides of the support part (2), and is secured and supported by a mounting part of a transportation vehicle (not shown here). The target wet transport container is the same type as the wet transport container (C) shown in (d) of FIG. 2, and a large number of heat radiation fins (F) are provided on the outer peripheral surface of the body, It is a cylindrical sealed pressure vessel having two pairs of trunnions (T) at both ends, and an assembly of spent nuclear fuel pins and a basket holding the assembly are housed inside the container. The basket is filled with water. And two pairs of trunnions (T) at both ends are
As shown in (c) of FIG. 1, the clamps (3) of the front and rear supporting portions (2) of the transportation base of this embodiment are freely rotatably gripped, so that they can be mounted on the transportation vehicle. Secured and supported.
【0013】ここで、本実施例の輸送架台では、その前
後の支持部(2) を、下端部に配置した昇降シリンダ(4)
によって昇降可能としているので、同 (c)図に示すよう
に、その前後の支持部(2) の一方を上昇させ、ないしは
双方を交番で昇降させることで、支持した湿式輸送容器
(C) の傾きを任意時点で変更することができる。Here, in the transportation platform according to the present embodiment, the lifting cylinder (4) having the supporting portions (2) at the front and rear thereof arranged at the lower end portion.
Since it can be lifted up and down by means of one of the supporting parts (2) in front of and behind it, as shown in FIG.
The slope of (C) can be changed at any time.
【0014】従って、本実施例の輸送架台では、輸送途
中において、昇降シリンダ(4) を作動させて支持した湿
式輸送容器(C) の傾きを変更し、この湿式輸送容器(C)
の内部に収容されている水が、共に収容されている使用
済核燃料の崩壊熱量に応じて、軸方向に流動することを
促して、内部の伝熱性能を高め、該湿式輸送容器(C)の
除熱機能を促進させることができる。更にまた、支持す
る湿式輸送容器(C) の傾斜角度を、収容された使用済核
燃料の崩壊熱量に対応し、計算上、最適な角度に設定す
ることで、前記従来技術のように、径方向の対流伝熱の
みに依存する湿式輸送容器での伝熱性能に比べて、 1.2
倍程度の伝熱効率の上昇が見込めるため、支持した湿式
輸送容器(C) の内部温度および内圧の上昇を抑制し、従
来より高い崩壊熱を発生する使用済核燃料も輸送するこ
とができる。Therefore, in the transportation platform of this embodiment, the inclination of the wet transportation container (C) supported by actuating the lifting cylinder (4) is changed during transportation, and the wet transportation container (C) is changed.
The water contained in the inside of the wet transport container (C) enhances the heat transfer performance of the inside by accelerating the flow of water in the axial direction according to the decay heat amount of the spent nuclear fuel contained together. The heat removal function of can be promoted. Furthermore, the inclination angle of the wet transport container (C) to be supported corresponds to the amount of decay heat of the spent nuclear fuel contained and is set to the optimum angle for calculation, so that the radial direction can be increased as in the prior art. Compared with the heat transfer performance in a wet transport container that depends only on the convective heat transfer of
Since it is expected that the heat transfer efficiency will be doubled, it is possible to suppress the increase in the internal temperature and internal pressure of the supported wet transport container (C), and also to transport the spent nuclear fuel that generates higher decay heat than before.
【0015】なお、本実施例の輸送架台では、前後の支
持部(2) は、それぞれの対の支柱部(2a)の下端部に昇降
シリンダ(4) を配設し、双方が個別ないしは交互に昇降
できる構成としたが、その前後の支持部(2) の一方を、
基台(1) 上に固定して立設し、他の一方の支持部(2) の
みを昇降させる構成としても、支持した湿式輸送容器
(C) の傾きを変更して、上記と同様の効果を得ることが
できる。また、その前後の支持部(2) それぞれの左右で
対の支柱部(2a)は、横桁(2b)で連結して1体化させた
が、この左右で対の支柱部(2a)は、それぞれの下端部に
配設した昇降シリンダ(4) の作動により同期して昇降で
きれば、横桁(2b)を省略して独立的に立設されても良
い。また、昇降シリンダ(4) は、各支柱部(2a)の下端部
に配設し、支持部(2) 自体を昇降させる構成としたが、
この昇降シリンダ(4)を、各支柱部(2a)上部と各クラン
プ(3) との間に介装し、これにより前後の支持部(2) を
基台(1) 上に固定して立設する一方で、その上端部の各
クランプ(3) を昇降させる構成とされても良い。また、
その昇降シリンダ(4) は、外部から油圧の供給を受けて
作動する油圧式のものとしたが、これは1例であって、
負荷される湿式輸送容器(C) の重さの分力に対抗して、
前後の支持部(2) もしくは各クランプ(3) を昇降させる
と共に、設定された各高さ位置で停止・保持できるもの
であれば、例えば、電動式のものとされて良いことは言
うまでもない。In the transportation platform of this embodiment, the front and rear supporting portions (2) are provided with lifting cylinders (4) at the lower end portions of the pair of supporting columns (2a), and both of them are individually or alternately arranged. Although it was configured to be able to move up and down, one of the front and rear support parts (2)
A supported wet transport container, even if it is fixedly installed on the base (1) and only the other support part (2) is moved up and down.
The same effect as above can be obtained by changing the inclination of (C). In addition, the pair of strut parts (2a) on the left and right of each of the front and rear support parts (2) are connected by a cross beam (2b) to be integrated, but the pair of strut parts (2a) on the left and right are As long as the lifting cylinders (4) provided at the respective lower ends can be moved up and down in synchronism with each other, the horizontal beams (2b) may be omitted to stand independently. In addition, the lifting cylinder (4) is arranged at the lower end of each column (2a) to raise and lower the support part (2) itself.
The lift cylinder (4) is interposed between the upper part of each column (2a) and each clamp (3), so that the front and rear supports (2) are fixed on the base (1). On the other hand, while being installed, the clamps (3) at the upper end may be moved up and down. Also,
The lifting cylinder (4) is a hydraulic type that operates by receiving hydraulic pressure from the outside, but this is an example.
To counter the component force of the weight of the wet transport container (C) that is loaded,
It goes without saying that, as long as the front and rear support portions (2) or the respective clamps (3) are moved up and down and stopped and held at the set height positions, for example, an electric type may be used.
【0016】[0016]
【発明の効果】以上に述べたように、本発明に係る輸送
架台によれば、使用済核燃料と共に水を収容した湿式輸
送容器を支持し、輸送用車両の搭載部に確実に固縛でき
てなお、輸送途中において、支持した湿式輸送容器の傾
きを変更し、その湿式輸送容器の内部に収容されている
水が、共に収容されている使用済核燃料の崩壊熱量に応
じて、軸方向に流動することを促して、内部の伝熱性能
を高め、これにより該湿式輸送容器の除熱機能を促進さ
せ、よって輸送中における該湿式輸送容器の内部温度お
よび内圧の上昇を抑制し、従来より高い崩壊熱を発生す
る使用済核燃料も輸送することができる。As described above, according to the transportation stand of the present invention, the wet transportation container containing water together with the spent nuclear fuel is supported and can be securely fastened to the mounting portion of the transportation vehicle. During transportation, the inclination of the supported wet transport container was changed, and the water contained in the wet transport container moved in the axial direction according to the decay heat amount of the spent nuclear fuel contained together. To increase the internal heat transfer performance, thereby promoting the heat removal function of the wet transport container, thereby suppressing the increase in the internal temperature and internal pressure of the wet transport container during transportation, Spent nuclear fuel that produces decay heat can also be transported.
【図1】本発明に係る輸送架台の1実施例の概要構成を
示す図面であって、 (a)図は一部を切欠いて示す正面
図、 (b)図は側面図、 (C)図は湿式輸送容器の支持およ
び作動状態の説明図である。1A and 1B are drawings showing a schematic configuration of one embodiment of a transportation platform according to the present invention, in which FIG. 1A is a front view with a part cut away, FIG. 1B is a side view, and FIG. FIG. 6 is an explanatory view of the support and operating state of the wet transport container.
【図2】従来の輸送架台の説明図であって、 (a)図は正
面図、 (b)図は側面図、 (c)図は湿式輸送容器の支持状
態の説明図、 (d)図は代表的な湿式輸送容器の外郭形状
の説明図である。2A and 2B are explanatory views of a conventional transportation base, where FIG. 2A is a front view, FIG. 2B is a side view, and FIG. 2C is an explanatory view of a supporting state of a wet transportation container; FIG. 3 is an explanatory view of an outer shape of a typical wet transportation container.
【符号の説明】 (1) --基台 (2) --支持部 (3) --クランプ (4) --昇降シリンダ (C) --湿式輸送容器 (T) --トラニオン[Explanation of symbols] (1) --Base (2) --Support (3) --Clamp (4) --Lift cylinder (C) --Wet transport container (T) --Trunion
Claims (1)
基台と、この基台の前後両端部上に立設され、その上端
部に左右で対のクランプを設けた前後の支持部とを備
え、使用済核燃料を水と共に収容した湿式輸送容器の両
端部に設けられた2対のトラニオンを、前記支持部の各
クランプで把持し、この湿式輸送容器を車両の搭載部に
固縛して輸送する湿式輸送容器の輸送架台において、前
記前後の支持部の内の少なくとも一方の支持部に、その
支持部自体ないしは上端部の対のクランプを昇降させる
シリンダ装置を設けてなることを特徴とする湿式輸送容
器の輸送架台。1. A flat plate-shaped base that is placed and connected to a mounting portion of a vehicle, and a front and a rear stand that are erected on both front and rear ends of the base and have a pair of left and right clamps provided at their upper ends. A pair of trunnions provided at both ends of a wet transportation container having a support portion and containing spent nuclear fuel together with water are held by respective clamps of the support portion, and the wet transportation container is mounted on a vehicle mounting portion. In a transportation platform for a wet transportation container to be bound and transported, at least one of the front and rear supporting portions is provided with a cylinder device for raising and lowering the supporting portion itself or a pair of upper end clamps. A transportation platform for a wet transportation container.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP6118657A JPH07325191A (en) | 1994-05-31 | 1994-05-31 | Transportation stage for wet transportation cask |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP6118657A JPH07325191A (en) | 1994-05-31 | 1994-05-31 | Transportation stage for wet transportation cask |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH07325191A true JPH07325191A (en) | 1995-12-12 |
Family
ID=14741997
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP6118657A Withdrawn JPH07325191A (en) | 1994-05-31 | 1994-05-31 | Transportation stage for wet transportation cask |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH07325191A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2003098289A (en) * | 2001-09-21 | 2003-04-03 | Hitachi Ltd | Method and facility for transporting fuel cask |
KR100704752B1 (en) * | 2006-01-26 | 2007-04-09 | 한국원자력연구소 | Standard rod and exchange jig for measuring of oxide thickness by eddy current test |
JP2015087325A (en) * | 2013-10-31 | 2015-05-07 | 三菱重工業株式会社 | Radioactive material storage container support mechanism |
JP2018513969A (en) * | 2015-03-25 | 2018-05-31 | テーエヌ アンテルナシオナル | Apparatus for supporting a radioactive material transport / storage package comprising a shroud for guiding air for cooling the package by natural convection |
-
1994
- 1994-05-31 JP JP6118657A patent/JPH07325191A/en not_active Withdrawn
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2003098289A (en) * | 2001-09-21 | 2003-04-03 | Hitachi Ltd | Method and facility for transporting fuel cask |
KR100704752B1 (en) * | 2006-01-26 | 2007-04-09 | 한국원자력연구소 | Standard rod and exchange jig for measuring of oxide thickness by eddy current test |
JP2015087325A (en) * | 2013-10-31 | 2015-05-07 | 三菱重工業株式会社 | Radioactive material storage container support mechanism |
JP2018513969A (en) * | 2015-03-25 | 2018-05-31 | テーエヌ アンテルナシオナル | Apparatus for supporting a radioactive material transport / storage package comprising a shroud for guiding air for cooling the package by natural convection |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 20010731 |