JPH08233985A - Storage facility of spent nuclear fuel - Google Patents
Storage facility of spent nuclear fuelInfo
- Publication number
- JPH08233985A JPH08233985A JP7059933A JP5993395A JPH08233985A JP H08233985 A JPH08233985 A JP H08233985A JP 7059933 A JP7059933 A JP 7059933A JP 5993395 A JP5993395 A JP 5993395A JP H08233985 A JPH08233985 A JP H08233985A
- Authority
- JP
- Japan
- Prior art keywords
- support plate
- rack support
- spring shaft
- rack
- pit
- 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- Withdrawn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
- Supports For Pipes And Cables (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、高密度ラックを用いた
使用済原子燃料の貯蔵設備に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a spent nuclear fuel storage facility using a high density rack.
【０００２】[0002]
【従来の技術】原子炉で使用された原子燃料は、原子炉
から取出された直後は放射性物質による崩壊熱を持って
いるため、貯蔵ピット内の水中で一定期間保管される。
この貯蔵ピットには、筒状のセルまたはアングルを組む
ことによって複数の原子燃料を収容できるようにしたラ
ックが備わっているが、燃料同士の間隔は臨界性を考慮
して一定以上の間隔を空けるようになっている。2. Description of the Related Art A nuclear fuel used in a nuclear reactor is stored in water in a storage pit for a certain period because it has decay heat due to radioactive substances immediately after being taken out from the nuclear reactor.
This storage pit is equipped with a rack that can accommodate multiple nuclear fuels by assembling cylindrical cells or angles, but the spacing between fuels should be a certain distance or more considering criticality. It is like this.
【０００３】ところで近年、この使用済燃料保管ラック
に中性子吸収材を組合せて、従来より狭い間隔の、いわ
ゆる高密度ラックを採用する事により貯蔵能力の強化が
図られている。By the way, in recent years, the storage capacity has been enhanced by combining a neutron absorbing material with this spent fuel storage rack and adopting a so-called high-density rack having a narrower space than before.
【０００４】従来の高密度ラックは、図７に示すよう
に、ラックセル２挿入用の孔２ａをあけた上下２枚また
はそれ以上のラック支持板９を、夫々が水平になるよう
に支柱Ｓを用いて組立て、ピットの側壁１ａに固定した
埋込板１ｂを介して、これらラック支持板９をピット側
壁１ａから固定するように支持する形となっている。In a conventional high-density rack, as shown in FIG. 7, two or more rack support plates 9 above and below each having a hole 2a for inserting a rack cell 2 are provided, and a column S is provided so that each of them is horizontal. The rack support plate 9 is assembled and used to fix the rack support plate 9 from the pit side wall 1a through the embedded plate 1b fixed to the pit side wall 1a.
【０００５】[0005]
【発明が解決しようとする課題】しかしながら、使用済
燃料ラックは、使用済燃料を内包するという性質上、使
用済燃料の崩壊熱により温度が上昇し、熱膨張する。こ
の時、ラック支持板を前述の如くピット側壁に固定する
という構造を取った場合、このピットの側壁に過大な力
が加わる。従って、ラック支持板はある程度自由に動け
るようにしておかねばならない。However, since the spent fuel rack contains the spent fuel, the temperature of the spent fuel rack rises due to the decay heat of the spent fuel and the thermal expansion occurs. At this time, if the rack support plate is fixed to the side wall of the pit as described above, an excessive force is applied to the side wall of the pit. Therefore, the rack support plate must be allowed to move to some extent.
【０００６】一方、地震時等にはラック支持板の過大な
動きを規制するため、ラック支持板を壁面から支えてお
く必要がある。この方法として、最大変位を規制した滑
り構造、例えば図６に示すようなＴ字型の支持部材１０
をＣ字型レール部材１１に組み込んだ構造を使用する方
法も考えられるが、この構造を複数用いて支える場合、
施工時の誤差や、ラック支持板端面あるいは埋込板表面
の反りにより、最小２つ、例えば両端の支持部材のみで
支えられてしまう可能性がある。On the other hand, it is necessary to support the rack support plate from the wall surface in order to prevent excessive movement of the rack support plate during an earthquake or the like. As this method, a sliding structure in which the maximum displacement is restricted, for example, a T-shaped support member 10 as shown in FIG.
Although a method of using a structure in which C is incorporated in the C-shaped rail member 11 is conceivable, when using a plurality of this structures,
There is a possibility that it will be supported by a minimum of two, for example, only the support members at both ends, due to an error in construction and a warp of the rack support plate end surface or the embedded plate surface.
【０００７】本発明は叙上の如き実状に対処し、上記使
用済燃料の貯蔵設備において、ラック支持板とピット側
壁との結合部に新規な構成を見出すことにより、上記ラ
ックの熱膨張に際してもピットの側壁に余分な力を与え
ず、また地震時等の横揺れに対してもラック支持板を適
切に支持せしめることを目的とするものである。The present invention copes with the above situation, and in the spent fuel storage facility, by finding a new structure at the joint between the rack support plate and the pit side wall, even when the rack is thermally expanded. The purpose of the present invention is not to give an extra force to the side wall of the pit and to properly support the rack support plate even against rolling such as an earthquake.
【０００８】[0008]
【課題を解決するための手段】すなわち、上記目的に適
合する本発明使用済原子燃料の貯蔵設備の特徴は、冷却
水を貯留するピットと、このピット内に立設され使用済
原子燃料を収容する多数のラックセルと、これらラック
セルを連結支持する略水平の複数段のラック支持板とを
備えた使用済原子燃料の貯蔵設備において、上記ラック
支持板周囲のピットの側壁側から上下１対の軸受け板を
複数突設し、この軸受け板に亘らせて棒状のばね軸を立
設すると共に、上記ラック支持板側の上記ばね軸と対応
する位置に嵌挿孔を穿設し、この嵌挿孔を上記軸受け板
の間でばね軸に嵌挿せしめ、かつ上記嵌挿孔縁部とばね
軸の周囲、および上記嵌挿孔周辺部と各軸受け板の間に
夫々、ラック支持板の熱膨張による伸張と変位を許容す
る間隙を形成せしめたところにある。That is, the feature of the spent nuclear fuel storage facility of the present invention which meets the above-mentioned object is that a pit for storing cooling water and a spent nuclear fuel which is erected in the pit to accommodate the spent nuclear fuel. In a spent nuclear fuel storage facility comprising a large number of rack cells and a plurality of substantially horizontal rack support plates for connecting and supporting these rack cells, a pair of upper and lower bearings is provided from the side wall of the pit around the rack support plates. A plurality of plates are projected, a rod-shaped spring shaft is erected over the bearing plate, and a fitting insertion hole is formed at a position corresponding to the spring shaft on the rack support plate side. A hole is fitted into the spring shaft between the bearing plates, and the rack support plate is expanded and displaced by thermal expansion, respectively, around the edge of the fitting hole and the spring shaft, and between the periphery of the fitting hole and each bearing plate. Form a gap that allows In the place it was.
【０００９】[0009]
【作用】上記本発明の貯蔵設備においては、使用済燃料
の崩壊熱によりラック支持板が膨張した場合でも、前記
嵌挿孔とばね軸との間、および嵌挿孔周辺部と軸受け板
の間に夫々形成した間隙によって、上記膨張によるラッ
ク支持板の伸長と変位とを許容し、これによりラックの
熱膨張によるピット側壁への力の作用を防止することが
可能となる。また、地震時等の横揺れに対し、上記間隙
以上にラック支持板が変位した場合は、上記ラック支持
板を前記ばね軸によって弾性的に支持せしめて、一部の
ばね軸のみに荷重がかかることを抑制すると共に、ピッ
ト側壁とラック支持板との干渉を防ぐことも可能であ
る。In the storage facility of the present invention described above, even when the rack supporting plate expands due to the decay heat of the spent fuel, it is respectively between the fitting insertion hole and the spring shaft, and between the fitting insertion hole peripheral portion and the bearing plate. The formed gap allows the expansion and displacement of the rack support plate due to the expansion, thereby preventing the action of force on the side wall of the pit due to the thermal expansion of the rack. Further, when the rack support plate is displaced by more than the above-mentioned gap due to rolling due to an earthquake or the like, the rack support plate is elastically supported by the spring shaft, and a load is applied only to a part of the spring shaft. It is possible to prevent this and also to prevent interference between the pit side wall and the rack support plate.
【００１０】[0010]
【実施例】以下さらに添付図面を参照して、本発明の実
施例を説明する。Embodiments of the present invention will be described below with reference to the accompanying drawings.
【００１１】図１は本発明実施例の使用済原子燃料の貯
蔵設備を示す要部拡大図、図２は同要部拡大断面図、図
３は同貯蔵設備を示す部分平面図、図４は同部分斜視図
である。FIG. 1 is an enlarged view of a main part showing a storage facility for spent nuclear fuel according to an embodiment of the present invention, FIG. 2 is an enlarged sectional view of the main part, FIG. It is the same partial perspective view.
【００１２】上記本発明実施例の貯蔵設備は、冷却水を
貯溜するピット１と、このピット１内に略垂直に配設さ
れ使用済原子燃料を収容する多数のラックセル２と、こ
のラックセル２を多数の挿入口２ａに嵌挿させることに
より連結支持する略水平の上下２段のラック支持板３と
を備えている。The storage equipment of the above-described embodiment of the present invention comprises a pit 1 for storing cooling water, a large number of rack cells 2 arranged substantially vertically in the pit 1 for storing spent nuclear fuel, and the rack cell 2. The rack support plate 3 includes two substantially horizontal rack support plates 3 that are connected and supported by being fitted into a large number of insertion openings 2a.
【００１３】そして、本発明実施例では、上記の如き貯
蔵設備において、ラック支持板３とピット側壁１ａとの
間に所要の間隔をあけると共に、図１、図２に示す如く
上記ラック支持板３周囲のピット側壁１ａ側から、この
側壁の一部である埋込板１ｂを介して上下１対の軸受け
板４、５を突設し、この軸受け板４、５に亘らせて円柱
棒状のばね軸６を略鉛直に立設している。上記軸受け板
４、５及びばね軸６は、図３、４等にも示すようにラッ
ク支持板３の全周に亘って形成されている。In the embodiment of the present invention, in the storage facility as described above, a required space is provided between the rack support plate 3 and the pit side wall 1a, and the rack support plate 3 is provided as shown in FIGS. A pair of upper and lower bearing plates 4 and 5 are projected from the surrounding pit side wall 1a side via an embedded plate 1b which is a part of the side wall, and the pair of bearing plates 4 and 5 is formed into a cylindrical rod shape. The spring shaft 6 is erected substantially vertically. The bearing plates 4 and 5 and the spring shaft 6 are formed over the entire circumference of the rack support plate 3 as shown in FIGS.
【００１４】一方、上記ラック支持板３側からは、上記
ばね軸６と対応する位置から略水平に取付金具７を突設
して、この取付金具７に嵌挿孔８を穿設し、図１、図２
に示す如くこの嵌挿孔８を上記軸受け板４、５の間で上
記ばね軸６に遊嵌させている。On the other hand, from the rack supporting plate 3 side, a mounting metal fitting 7 is projected substantially horizontally from a position corresponding to the spring shaft 6, and a fitting insertion hole 8 is formed in the mounting metal fitting 7. 1, Figure 2
As shown in FIG. 5, the fitting insertion hole 8 is loosely fitted to the spring shaft 6 between the bearing plates 4 and 5.
【００１５】上記嵌挿孔８の縁部と上記ばね軸６の周囲
には、ラック支持板３の熱膨張による伸長と変位を許容
する間隙Ｇ1 が形成されている。この間隙Ｇ1 の幅は、
ラック支持板３の熱膨張による伸長により，ほぼ埋めら
れる大きさとなっている。A gap G 1 is formed around the edge of the fitting hole 8 and the spring shaft 6 to allow the rack support plate 3 to expand and displace due to thermal expansion. The width of this gap G 1 is
The rack support plate 3 has a size that can be almost filled by expansion due to thermal expansion.
【００１６】また同様に、前記取付金具７の上記嵌挿孔
８の周辺部と前記軸受け板４、５の間にも、上記熱膨張
によるラック支持板３の伸長と変位を許容する間隙Ｇ2
が形成されている。Similarly, a gap G 2 which allows extension and displacement of the rack support plate 3 due to the thermal expansion is also provided between the peripheral portion of the fitting insertion hole 8 of the mounting member 7 and the bearing plates 4 and 5.
Are formed.
【００１７】なお、図５に示すものは、ばね軸６の例で
あり、このばね軸６では、一例としてばねに生じる応力
を低減するため軸方向に４分割している。ただし、材
料、直径を適当に選ぶ事により、分割数は４分割に限ら
ず、また、分割しない円柱とすることもできる。また、
この実施例では、ばね軸６は円柱状のものを例示してい
るが，その断面は円形以外の矩形等のものでも実現でき
る。FIG. 5 shows an example of the spring shaft 6, and the spring shaft 6 is divided into four parts in the axial direction in order to reduce the stress generated in the spring. However, by appropriately selecting the material and the diameter, the number of divisions is not limited to four, and it is also possible to use non-divided cylinders. Also,
In this embodiment, the spring shaft 6 is illustrated as having a cylindrical shape, but the cross-section can be realized with a rectangular shape other than a circular shape.
【００１８】そしてさらに、上記ばね軸６の力と変位の
関係は、ラック施工時のこのばね軸６と前記取付金具７
の嵌挿孔８の同心円度の許容誤差とピット側壁１ａの強
度により定める。Furthermore, the relationship between the force and displacement of the spring shaft 6 is as follows.
It is determined by the concentricity tolerance of the insertion hole 8 and the strength of the pit side wall 1a.
【００１９】しかして、上記本発明実施例の貯蔵設備に
おいては、使用済燃料の崩壊熱によりラック支持板３が
膨張した場合でも、嵌挿孔８とばね軸６の間、および嵌
挿孔８周辺部と軸受け板４、５の間に夫々形成した間隙
Ｇ1 、Ｇ2 、によって、上記膨張によるラック支持板３
の伸長と変位とを許容し，これよりラックの熱膨張によ
るピット側壁１ａへの力の作用を防止することが可能で
ある。Therefore, in the storage facility of the above-described embodiment of the present invention, even when the rack support plate 3 expands due to the decay heat of the spent fuel, the space between the fitting insertion hole 8 and the spring shaft 6 and the fitting insertion hole 8 are not included. Due to the gaps G 1 and G 2 formed between the peripheral portion and the bearing plates 4 and 5, respectively, the rack support plate 3 due to the expansion described above.
It is possible to allow the expansion and displacement of the pit, and thereby prevent the action of the force on the pit side wall 1a due to the thermal expansion of the rack.
【００２０】また、地震時にラック支持板３に横加速が
加わった時、ラック支持板３は水平方向に変位するが、
間隙Ｇ1 以上にラック支持板３が変位した場合は、上記
ラック支持板３を前記ばね軸６によって弾性的に支持せ
しめて、一部のばね軸６のみに荷重がかかることを抑制
すると共に、ピット側壁１ａとラック支持板３との干渉
を防ぐことが可能である。When lateral acceleration is applied to the rack support plate 3 during an earthquake, the rack support plate 3 is displaced in the horizontal direction,
When the rack support plate 3 is displaced beyond the gap G 1 , the rack support plate 3 is elastically supported by the spring shafts 6 to prevent a load from being applied to only a part of the spring shafts 6, It is possible to prevent interference between the pit side wall 1a and the rack support plate 3.
【００２１】以上、本発明実施例を説明したが、ラック
支持板３の垂直方向の支持は、図４に示す支柱Ｓによっ
て担持させることが可能である。Although the embodiment of the present invention has been described above, the vertical support of the rack support plate 3 can be carried by the column S shown in FIG.
【００２２】[0022]
【発明の効果】以上説明したように、本発明の使用済原
子燃料の貯蔵設備は、ラック支持板周囲のピットの側壁
側から上下１対の軸受け板を複数突設し、この軸受け板
に亘らせて棒状のばね軸を立設すると共に、上記ラック
支持板側の上記ばね軸と対応する位置に嵌挿孔を穿設
し、この嵌挿孔を上記軸受け板の間でばね軸に嵌挿せし
め、かつ上記嵌挿孔縁部とばね軸の周囲、および上記嵌
挿孔周辺部と各軸受け板の間に夫々、ラック支持板の熱
膨張による伸張と変位を許容する間隙を形成せしめたも
のであり、使用済燃料の崩壊熱によりラック支持板が膨
張した場合でも、前記嵌挿孔とばね軸との間、および嵌
挿孔周辺部と軸受け板の間に夫々形成した間隙によっ
て、上記膨張によるラック支持板の伸長と変位とを許容
し、これによりラックの熱膨張によるピット側壁への力
の作用を防止することができ、またさらに、地震時等の
横揺れに対し、上記間隙以上にラック支持板が変位した
場合は、上記ラック支持板を前記ばね軸によって弾性的
に支持せしめて、一部のばね軸のみに荷重がかかること
を抑制すると共に、ピット側壁とラック支持板との干渉
も防止するとの顕著な効果を奏するものである。As described above, in the spent nuclear fuel storage facility of the present invention, a plurality of pairs of upper and lower bearing plates are projected from the side wall of the pit around the rack support plate and extend over the bearing plates. And a rod-shaped spring shaft is erected, and a fitting insertion hole is formed at a position corresponding to the spring shaft on the rack support plate side, and the fitting insertion hole is fitted into the spring shaft between the bearing plates. In addition, a gap for allowing expansion and displacement due to thermal expansion of the rack support plate is formed between the edge portion of the fitting insertion hole and the periphery of the spring shaft, and between the peripheral portion of the fitting insertion hole and each bearing plate, Even if the rack support plate expands due to the decay heat of the spent fuel, the gaps formed between the fitting insertion hole and the spring shaft and between the fitting insertion hole peripheral portion and the bearing plate cause the expansion of the rack supporting plate due to the expansion. Allows extension and displacement, which allows racks It is possible to prevent the action of force on the side wall of the pit due to thermal expansion, and, further, when the rack support plate is displaced beyond the gap due to the rolling due to an earthquake or the like, the rack support plate is attached to the spring shaft. With the elastic support, it is possible to prevent the load from being applied only to a part of the spring shaft, and to prevent the interference between the pit side wall and the rack support plate.
【図１】本発明実施例の使用済原子燃料貯蔵設備を示す
要部拡大図である。FIG. 1 is an enlarged view of essential parts showing a spent nuclear fuel storage facility according to an embodiment of the present invention.
【図２】同要部拡大断面図である。FIG. 2 is an enlarged sectional view of the main part.
【図３】同貯蔵設備を示す部分平面図である。FIG. 3 is a partial plan view showing the storage facility.
【図４】同部分斜視図である。FIG. 4 is a partial perspective view of the same.
【図５】ばね軸の例を示す斜視図である。FIG. 5 is a perspective view showing an example of a spring shaft.
【図６】従来のラック支持板とピット側壁との結合例を
示す部分拡大図である。FIG. 6 is a partially enlarged view showing an example of a conventional rack support plate and a pit side wall coupled together.
【図７】従来の使用済燃料の貯蔵設備を示す断面斜視図
である。FIG. 7 is a sectional perspective view showing a conventional spent fuel storage facility.
１ ピット １ａ ピット側壁 ２ ラックセル ２ａ 挿入孔 ３ ラック支持板 ４，５ 軸受け板 ６ ばね軸 ７ 取付金具 ８ 嵌挿孔 Ｇ1 ，Ｇ2 間隙 Ｓ 支柱1 pit 1a pit side wall 2 rack cell 2a insertion hole 3 rack support plate 4, 5 bearing plate 6 spring shaft 7 mounting bracket 8 fitting insertion hole G 1 , G 2 gap S strut
Claims (1)
に立設され使用済原子燃料を収容する多数のラックセル
と、これらラックセルを連結支持する略水平の複数段の
ラック支持板とを備えた使用済原子燃料の貯蔵設備にお
いて、上記ラック支持板周囲のピットの側壁側から上下
１対の軸受け板を複数突設し、この軸受け板に亘らせて
棒状のばね軸を立設すると共に、上記ラック支持板側の
上記ばね軸と対応する位置に嵌挿孔を穿設し、この嵌挿
孔を上記軸受け板の間でばね軸に嵌挿せしめ、かつ上記
嵌挿孔縁部とばね軸の周囲、および上記嵌挿孔周辺部と
各軸受け板の間に夫々、ラック支持板の熱膨張による伸
張と変位を許容する間隙を形成せしめたことを特徴とす
る使用済原子燃料の貯蔵設備。1. A pit for storing cooling water, a large number of rack cells standing in the pit for containing spent nuclear fuel, and a plurality of substantially horizontal rack support plates for connecting and supporting these rack cells. In the spent nuclear fuel storage facility, a pair of upper and lower bearing plates are provided so as to project from the side wall of the pit around the rack support plate, and a rod-shaped spring shaft is erected over the bearing plates. , A fitting insertion hole is formed at a position corresponding to the spring shaft on the rack support plate side, and the fitting insertion hole is fitted into the spring shaft between the bearing plates, and the fitting insertion hole edge portion and the spring shaft are A storage facility for spent nuclear fuel, characterized in that a gap allowing expansion and displacement due to thermal expansion of a rack support plate is formed in the periphery and between the peripheral portion of the fitting insertion hole and each bearing plate, respectively.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7059933A JPH08233985A (en) | 1995-02-22 | 1995-02-22 | Storage facility of spent nuclear fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7059933A JPH08233985A (en) | 1995-02-22 | 1995-02-22 | Storage facility of spent nuclear fuel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH08233985A true JPH08233985A (en) | 1996-09-13 |
Family
ID=13127436
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP7059933A Withdrawn JPH08233985A (en) | 1995-02-22 | 1995-02-22 | Storage facility of spent nuclear fuel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH08233985A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009109302A (en) * | 2007-10-29 | 2009-05-21 | Toshiba Corp | Seismic reinforcement structure and method for spent fuel storage rack |
| JP2014145787A (en) * | 2014-05-07 | 2014-08-14 | Mitsubishi Heavy Ind Ltd | Nuclear fuel storage rack and nuclear fuel storage rack group |
| JP2014145788A (en) * | 2014-05-07 | 2014-08-14 | Mitsubishi Heavy Ind Ltd | Nuclear fuel storage rack and nuclear fuel storage rack group |
| JP2016197034A (en) * | 2015-04-02 | 2016-11-24 | 株式会社東芝 | Corium holding device, and atomic reactor facility |
-
1995
- 1995-02-22 JP JP7059933A patent/JPH08233985A/en not_active Withdrawn
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009109302A (en) * | 2007-10-29 | 2009-05-21 | Toshiba Corp | Seismic reinforcement structure and method for spent fuel storage rack |
| JP2014145787A (en) * | 2014-05-07 | 2014-08-14 | Mitsubishi Heavy Ind Ltd | Nuclear fuel storage rack and nuclear fuel storage rack group |
| JP2014145788A (en) * | 2014-05-07 | 2014-08-14 | Mitsubishi Heavy Ind Ltd | Nuclear fuel storage rack and nuclear fuel storage rack group |
| JP2016197034A (en) * | 2015-04-02 | 2016-11-24 | 株式会社東芝 | Corium holding device, and atomic reactor facility |
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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: 20020507 |