GB2337722A - Dry storage vault - Google Patents
Dry storage vault Download PDFInfo
- Publication number
- GB2337722A GB2337722A GB9811538A GB9811538A GB2337722A GB 2337722 A GB2337722 A GB 2337722A GB 9811538 A GB9811538 A GB 9811538A GB 9811538 A GB9811538 A GB 9811538A GB 2337722 A GB2337722 A GB 2337722A
- Authority
- GB
- United Kingdom
- Prior art keywords
- vault
- concrete
- members
- chamber
- air outlet
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F7/00—Shielded cells or rooms
- G21F7/015—Room atmosphere, temperature or pressure control devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/06—Magazines for holding fuel elements or control elements
- G21C19/07—Storage racks; Storage pools
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/06—Details of, or accessories to, the containers
- G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Filling Or Discharging Of Gas Storage Vessels (AREA)
Abstract
Canisters 400 are stored above ground in separate chambers of a concrete vault. The vault is constructed from pre-cast concrete sections 120, 140, 150. Each chamber has a stainless steel liner 450, defining inner and outer annular spaces 510, 520 between the hot canister wall 402 and the concrete wall 465. Cooling air flows through both spaces 510,520 by natural convection. Cold air flows in through base level vents 170. Hot air from the outer annular spaces discharges through upper vents 172 formed in the concrete and that from the inner space discharges through a gap 436 between a metal lid 430 and flanges 432, 434. Slots 532 are formed between inner and outer annular spaces to allow discharge of all hot air even if one vent is to become blocked. The concrete walls are cooled by further ducts formed as an integral part of the pre-cast structures.
Description
2337722 1 DEy Storage Vault This invention relates to dry storage vaults.
It particularly relates to dry storage vaults for the storage of spent nuclear fuel.
In a known type of dry storage vault, canisters of spent fliel are arranged vertically in a chamber and air is caused to pass horizontally over the canisters by thermosyphon action. The chamber communicate with a flue which draws hot air upwards and causes cool air to be drawn into the chamber. Thus heat is removed by natural convection without the need for auxiliary cooling fans. Such a vault is described in 'lle developed technology of modular vault dry storage", Nuclear Engineering International April, 1984. While this has proved to be an effective method of dealing with spent fuel, it does have a number of disadvantages. The chamber and flue have to be built on-site to me the risk of radiation leakage from the fuel, the construction must be built on site using poured concrete. Suitable foundations must be provided for the resultant massive structure, and all the machinery required for vault construction must be transported to the site where the vault is to be constructed.
The present invention arose from an attempt to provide an improved dry storage vault. The invention provides a dry storage vault for heatemitting radioactive material contained within a canister, the vault Omprising: a concrete body having a chamber to accommodate the canister with its long axis substantially vertical, a cylindrical liner arranged within the chamber to define a first annular space between the inner wall of the 1 --- 2 1 chamber and the outer wall of the liner, the liner being arranged to accommodate the canister therein with a clearance, the clearance defining a second annular space, air inlet means at the lower end of the chamber communicating with the first and second annular spaces at the lower ends thereof, and air outlet means at the upper end of the chamber communicating with the first and second annular spaces at the upper ends thereof Unlike the prior art, each canister has its own cooling arrangement. Unlike the prior art, a vault in accordance with the invention does not require the provision of a large building with its attendant massive foundation. It can be assembled from precast units manufactured off site and only requires a suitable hard surface capable of supporting the weight of the vault. The provision of the liner reduces the temperature to which the concrete structural members are subjected, resulting in reduced thermal stresses and reducing the likelihood of degradation of the concrete.
Embodiments of the invention will now be described, by way of nonlimiting example only, with reference to the drawings in which:
Fig 1 shows an isometric view of a first embodiment of the invention; Fig 2 shows an exploded view of fig 1; Fig 3 shows an exterior plan view of fig 1; 3 Fig 4 shows a sectioned elevation view of fia 1 on line WAV of fig 3; c Fig 5 shows a detail of fig 4 on an enlarged scale; Fig 6 shows a sectioned view of fig 1 along line VI-VI of fig 3; c Fig 7 shows a scrap view of fig 1 along line VIII-VH of fig 3; Fig 8 shows a side elevation view of fig 1; Fig 9 shows an end elevation view of fig 1; Fig 10 shows a second embodiment of the invention; and Fig 11 shows a third embodiment of the invention.
Referring now to figures 1-9 the vault consists of a number of precast concrete components, namely, end base members 110, centre base members 120, end top members 130, centre top members 140, side wall members 150, and end wall members 160. The vault also comprises a number of cylindrical steel liners 450 whose function will be described later, flange members 432, 434, and lids 430.
Members 110, 120, 130 and 140 have a number of channels which provide ducts for flow of air therethrough when the vault is in its assembled state. The members are n C 4 provided with steps which serve both to assist assembly and to provide a tortuous path for radiation to prevent leakage thereof. The members also have channels 180, 182 which, after assembly, are fitted with concrete 186 to secure the units together and provide a monolithic structure.
Referring now to figs 2, 4 and 5, the lower and upper members 110, 130 and 120, 140 have cylindrical bores which, in the assembled vault, constitute chambers in which fuel canisters 400 are accommodated. Each chamber has a wall 460 constituting a concrete surface. Each chamber is provided with a stainless steel liner 450 arranged so as to provide a first annular gap 5 10 between the fuel canister 400 and the inner surface 452 of the liner 450, and a second annular gap 520 between the outer surface 454 of liner 450 and the concrete wall 460. These annular gaps allow passage of cooling air to flow therethrough as will be described later. As seen in fig 5, the bottom of the cylindrical liner 450 is provided with a number of apertures 530 to allow passage of air therethrough.
The base members 110, 120, have air ducts 170 to allow entry of air from the atmosphere into the interior of the chamber 400 at the base thereof via slots 470 through the lower inner concrete wall 465 of the chamber, and to pass into annular gaps 5 10, 520.
The top members 130, 140 have ducts 172 to allow air which has flowed via annular gap 520 to pass to the atmosphere via slots 475 through the upper inner concrete wall 465 of the chamber. The openings of ducts 170, 172 have screens to prevent entrance of birds or other animals.
The top of the liner 450 terminates a first steel flange 434 which is sealed to its respective concrete member 410, 420. A second steel flange 432 is fitted over the first flange 434. A steel lid 430 is fitted over the second flange. The lid 406 of the canister 400 locates within but does not touch the first flange 434 so as to provide a labyrinthine passage for hot air. The lid and flange are such to leave a gap 436 through which air which has flowed via annular gap 5 10 to pass to the atmosphere.
The air at the top of the inner annular gap 510 can reach a temperature which could cause long-term damage to concrete. Hence this very hot air is normally allowed to escape by an air path whose walls are constituted by steel members and thus does not come into direct contact with concrete.
The air at the top of the outer annular gap 520 will not reach a temperature sufficiently high to cause damage to concrete and hence can be allowed to escape via ducts cast into the concrete side members and whose walls consist of the concrete of which the walls are cast. This is also the situation when gap 436 i accidentally blocked.
A number of communication slots 532 in the liner 450 provide communication between the inner and outer annular spaces at the top of the chamber. This provides an alternative non-preferential flow path via annular gap 520 and ducts 172 to atmosphere in the event 6 c : r.
1 that gap 436 is accidentally blocked. The hot air from annular gap 510 is diluted and cooled by mixing with the cooler air flow in annular gap 520.
The base 453 of the liner 450 is supported by spacing members 480 above the base of the chamber to provide a space 482 to allow free passage of air from inlet duct 170 to the entire lower periphery of the liner 450 via slot 470.
As shown in fig 6, bars 3 10 are located in grooves provided therefor to cover the joins between adjacent base members 110, 120 and top members 130, 140. These bars provide a labyrinthine path to inhibit egress of stray radiation.
The vault is designed to be used in the open air. Having prepared a suitable hard standing, the individual units, which may be fabricated offsite using conventional concrete casting techniques, are assembled. Fuel canisters 400 are then placed in the is chambers as required and the flanges 432 and lids 430 fitted. Heat from the fuel in the canisters causes the surface temperature of the outer cylindrical wall 402 of the canister 400 to rise. Part of this heat is carried away by convection by air in annular gap 5 10, the remainder as radiant heat. This radiant heat falls on liner 450 and causes its temperature to rise. The inner surface 452 is blackened to minimise the radiation of heat back to surface 402.
Some heat is lost from the liner 450 by convection, both from its inner surface 452 by air in inner annular gap 510 and, from its outer surface by air in outer annular gap 520.
7 The remainder of the heat is lost by radiation from its outer surface 454. The outer surface 454 is a natural stainless steel finish to enhance the surface radiation of heat.
This radiant heat warms the concrete surface 460 of the chamber. Some of this heat is absorbed by the concrete by conduction, the remainder is carried away from surface 460 by convection by air in the outer annular gap 520.
Thus the air in both annular gaps 510 and 520 becomes heated and rises. In general, air in gap 510 will rise and leave the chamber via lid 430, while air in gap 520 will leave via the vents 172. As noted above, in the event of a blockage, the communication slots in the liners allow air in gap 5 10 to leave via vent 172 and air in gap 520 to leave via lid 430.
The heat absorbed by the concrete will cause its temperature to rise. Some of this heat is removed by further ducts 700 cast into the upper and lower members. These ducts communicate with the inlet and outlet ducts 170, 172.
The surface temperature of the canisters 400 will normally be sufficiently high that, in the absence of liner 450, heat radiated from the canister would cause the temperature of the concrete 460 to rise to a level which could give rise to long-term damage of the concrete. Liner 450 prevents the temperature of wall 460 from becoming excessive, both by providing a shield from direct thermal radiation and by increasing the surface area from which heat may be transferred to the air by convection. This reduction in concrete temperature allows conventional concrete to be used without the need for special 8 strengthening members.
It will be seen that the vault cooling system is driven by the natural buoyancy of heated air, with the stored irradiated fuel providing the source of heat. The cooling system air flow is a function of the decay heat of the stored fuel: the hotter the fuel, the greater the bouyancy of heated air, the faster the air flow, the greater the cooling effect of the air.
This arrangement thus provides a self-regulating, inherently reliable, cooling system with diversity of flow paths in the event of accidental blockage.
is Loading and loading operations will now be described.
The loading operation starts when the Transfer Cask and canister arrives at the Vault on the back of a tow trailer. The Canister Transfer Cask is removed from the trailer using the overhead crane and lifted onto the vault storage location. The Cover plate from the storage location has been previously removed by the Crane. The shield doors on the base of the transfer cask are opened to permit the canister to be lowered out of the Transfer Cask into the vault storage position by the overhead Crane. The vault shielding integrity is complete by the integral shield plug that is part of the canister lid. The Transfer Cask shield doors are closed and the Transfer Cask removed from the vault. After the vault Cover Plate is replaced the storage transfer operation is complete.
When the canister has to be removed from the Vault it can be placed directly into a transportation cask without having to return to a pool facility. A stand is located adjacent 9 to the Vault and this is used to support the transport cask in a vertical position ready to receive the canister. An adaptor ring is docked on top of the transport cask to permit it to interface with the Vault transfer cask. The canister is removed from the vault using the overhead Crane and Transfer Cask which is then docked onto the Transportation Cask. The canister can then be transferred directly into the Transport Cask from the Transfer Cask. After the Transfer Cask has been removed, the lid to the Transportation cask is fitted and the Cask loaded onto a trailer for off-site shipment.
While the above embodiment provided storage for eight canisters, the invention can be applied to greater or lesser numbers.
Figure 10 corresponds with fig 3, and shows an arrangement for four canisters.
Compared with the first embodiment this uses the same end units 110, 130 and 160 as the first embodiment and only requires the provision of a special side wall in place of the side wall 150.
Figure 11 corresponds with fig 3, and shows an arrangement for use with six canisters.
This arrangement uses two sets of end units 110, 130 and end walls 160 and only one set of centre units 120, 140. It only requires the provision of a special side wall in place of side wall 150.
It will be seen that, compared with prior art arrangement, vaults in accordance with the invention can be manufactured off-site in prefabricated form, only requiring assembly
0 0 C 1 on site.
It also makes it possible to construct a range of vaults of different sizes using a number of components common to all designs, only a minimal number of components being peculiar to the particular design.
A number of modification are possible within the scope of the invention.
Although in the described embodirnents the flanges and cap are stee any other suitable material, metal or non-metal, may be used. It is only necessary that the materials be capable of withstanding relatively high temperatures and low levels of neutron radiation without deterioration, and provide adequate radiation shielding.
The vault may be used to store any suitable heat-emitting radioactive material in canisters, whether spent nuclear fuel or high level waste, and is not peculiar to any one type of material.
If the installation is such that it can be ensured that the exit vents for hot air cannot become blocked, the communication slots at the top of the chamber affording communication between the inner and outer annular spaces may be omitted. This will ensure that the hotter air from the inner annular chamber never come into contact with concrete at all.
11
Claims (15)
1. A dry storage vault for heat-emitting radioactive material disposed within a canister, the vault comprising a concrete body having a chamber to accommodate the canister with its long axis substantially vertical, a cylindrical liner arranged within the chamber to define a first annular space between the inner wall of the chamber and the outer wall of the liner, the liner being arranged to accommo.date the canister therein with a clearance, the 10 clearance defining a second annular space, air inlet means at the lower end of the chamber communicating with the first and second annular spaces at the lower ends thereof, and air outlet means at the upper end of the chamber communicating with the first and second annular spaces at the upper ends thereof.
2. A vault as claimed in claim 1 in which the liner comprises a number of apertures at the upper end thereof affording communication between the first and second annular spaces.
3. A dry storage vault as claimed in claim 1 or 2 in which the concrete body comprises cooling duct means arranged to cool the concrete body.
A vault as claimed in claim 2 or 3 in which the cooling duct means 12 communicates with the air inlet and air outlet means.
5. A vault as claimed in any of claims 1-4 in which the air outlet means comprises a first air outlet coupled to the first annular space and a second air outlet coupled to the 5 second annular space.
6. A vault as claimed in claim 5 in which the second air outlet means comprises duct work arranged between the second annular space and the second air outlet vent, in which the duct work and vent comprise heat-resistant members.
7. A vault as claimed in claim 6 in which the heat-resistant members comprise metal members.
8. A vault as claimed in any preceding claim in which the vault comprises a 15 plurality of precast concrete members.
9. A vault as claimed in claim 8 comprising baffle means arranged to cover at least one joint between abutting members to inhibit escape of radiation.
10. A vault as claimed in claim 8 in which the mating surfaces between abutting members are shaped to provide a baffle to inhibit escape of radiation.
A vault as claimed in any one of claims 8, 9, or 10 in which at least one joint 13 between abutting members is provided with a void arranged to be filled with concrete during assembly to secure the abutting members together.
12. A vault as claimed in any preceding claims comprising a plurality of chambers.
13. A method of constructing a vault as claimed in any preceding claims comprising the steps of prefabricating individual concrete components, and; assembling said prefabricated concrete components on-site.
14. A dry storage vault substantially as described with reference to or as illustrated in figures 1-9, figure 10 or figure 11 of the drawings.
15. A method of constructing a dry storage vault substantially as described.
Priority Applications (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB9811538A GB2337722B (en) | 1998-05-29 | 1998-05-29 | Dry storage vault |
ZA9903676A ZA993676B (en) | 1998-05-29 | 1999-05-31 | Dry storage vault. |
PCT/GB1999/001726 WO1999063544A1 (en) | 1998-05-29 | 1999-06-01 | Dry storage vault |
AU42750/99A AU4275099A (en) | 1998-05-29 | 1999-06-01 | Dry storage vault |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB9811538A GB2337722B (en) | 1998-05-29 | 1998-05-29 | Dry storage vault |
Publications (3)
Publication Number | Publication Date |
---|---|
GB9811538D0 GB9811538D0 (en) | 1998-07-29 |
GB2337722A true GB2337722A (en) | 1999-12-01 |
GB2337722B GB2337722B (en) | 2002-01-09 |
Family
ID=10832885
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB9811538A Expired - Fee Related GB2337722B (en) | 1998-05-29 | 1998-05-29 | Dry storage vault |
Country Status (4)
Country | Link |
---|---|
AU (1) | AU4275099A (en) |
GB (1) | GB2337722B (en) |
WO (1) | WO1999063544A1 (en) |
ZA (1) | ZA993676B (en) |
Cited By (18)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6718000B2 (en) * | 2002-02-06 | 2004-04-06 | Holtec International, Inc. | Ventilated vertical overpack |
JP2008538140A (en) * | 2005-03-25 | 2008-10-09 | ホルテック・インターナショナル・インコーポレーテッド | System and method for storing high-level waste |
WO2006086766A3 (en) * | 2005-02-11 | 2009-04-23 | Holtec International Inc | Manifold system for a ventilated storage for high level nuclear waste |
US20090159550A1 (en) * | 2007-12-22 | 2009-06-25 | Singh Krishna P | System and method for the ventilated storage of high level radioactive waste in a clustered arrangement |
US8098790B2 (en) | 2004-03-18 | 2012-01-17 | Holtec International, Inc. | Systems and methods for storing spent nuclear fuel |
US8718220B2 (en) | 2005-02-11 | 2014-05-06 | Holtec International, Inc. | Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment |
US8995604B2 (en) | 2009-11-05 | 2015-03-31 | Holtec International, Inc. | System, method and apparatus for providing additional radiation shielding to high level radioactive materials |
US9443625B2 (en) | 2005-03-25 | 2016-09-13 | Holtec International, Inc. | Method of storing high level radioactive waste |
WO2017014666A1 (en) * | 2015-07-23 | 2017-01-26 | Общество С Ограниченной Ответственностью Промышленная Компания "Технология Металлов" | Method of preparing radioactive dust for long-term storage or burial and device for the implementation thereof |
US10217537B2 (en) | 2010-08-12 | 2019-02-26 | Holtec International | Container for radioactive waste |
US10332642B2 (en) | 2009-05-06 | 2019-06-25 | Holtec International | Apparatus for storing and/or transporting high level radioactive waste, and method for manufacturing the same |
US10418136B2 (en) | 2010-04-21 | 2019-09-17 | Holtec International | System and method for reclaiming energy from heat emanating from spent nuclear fuel |
CN110867269A (en) * | 2019-11-27 | 2020-03-06 | 中广核工程有限公司 | Spent fuel dry-type storage vertical storage module |
US10811154B2 (en) | 2010-08-12 | 2020-10-20 | Holtec International | Container for radioactive waste |
US10892063B2 (en) | 2012-04-18 | 2021-01-12 | Holtec International | System and method of storing and/or transferring high level radioactive waste |
US11373774B2 (en) | 2010-08-12 | 2022-06-28 | Holtec International | Ventilated transfer cask |
US11569001B2 (en) | 2008-04-29 | 2023-01-31 | Holtec International | Autonomous self-powered system for removing thermal energy from pools of liquid heated by radioactive materials |
US11887744B2 (en) | 2011-08-12 | 2024-01-30 | Holtec International | Container for radioactive waste |
Families Citing this family (4)
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---|---|---|---|---|
DE10135650B4 (en) * | 2001-07-21 | 2009-04-02 | Evonik Energy Services Gmbh | Method and device for storing containers containing heat-generating material |
WO2008097381A2 (en) | 2006-10-11 | 2008-08-14 | Holtec International, Inc. | Apparatus and method for transporting and/or storing radioactive materials |
US8905259B2 (en) | 2010-08-12 | 2014-12-09 | Holtec International, Inc. | Ventilated system for storing high level radioactive waste |
WO2013085638A1 (en) | 2011-10-28 | 2013-06-13 | Holtec International, Inc. | Method for controlling temperature of a radioactive waste storage system |
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US5564498A (en) * | 1994-09-16 | 1996-10-15 | Robatel | Device for cooling containments |
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EP0626030A1 (en) * | 1992-02-11 | 1994-11-30 | Allo Assmann | Waste storage facility and reinforced concrete supporting framework for such a storage facility |
FR2721430B1 (en) * | 1994-06-17 | 1996-09-13 | Cogema | Device and method for bag storage of materials releasing heat. |
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1998
- 1998-05-29 GB GB9811538A patent/GB2337722B/en not_active Expired - Fee Related
-
1999
- 1999-05-31 ZA ZA9903676A patent/ZA993676B/en unknown
- 1999-06-01 AU AU42750/99A patent/AU4275099A/en not_active Withdrawn
- 1999-06-01 WO PCT/GB1999/001726 patent/WO1999063544A1/en not_active Application Discontinuation
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GB1456860A (en) * | 1972-12-13 | 1976-12-01 | Technigaz | Enclosure for confining radio-active products or waste |
US5564498A (en) * | 1994-09-16 | 1996-10-15 | Robatel | Device for cooling containments |
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US20090159550A1 (en) * | 2007-12-22 | 2009-06-25 | Singh Krishna P | System and method for the ventilated storage of high level radioactive waste in a clustered arrangement |
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US10217537B2 (en) | 2010-08-12 | 2019-02-26 | Holtec International | Container for radioactive waste |
US11373774B2 (en) | 2010-08-12 | 2022-06-28 | Holtec International | Ventilated transfer cask |
US11887744B2 (en) | 2011-08-12 | 2024-01-30 | Holtec International | Container for radioactive waste |
US10892063B2 (en) | 2012-04-18 | 2021-01-12 | Holtec International | System and method of storing and/or transferring high level radioactive waste |
US11694817B2 (en) | 2012-04-18 | 2023-07-04 | Holtec International | System and method of storing and/or transferring high level radioactive waste |
WO2017014666A1 (en) * | 2015-07-23 | 2017-01-26 | Общество С Ограниченной Ответственностью Промышленная Компания "Технология Металлов" | Method of preparing radioactive dust for long-term storage or burial and device for the implementation thereof |
RU2691099C2 (en) * | 2015-07-23 | 2019-06-11 | Общество С Ограниченной Ответственностью Промышленная Компания "Технология Металлов" | Method of preparing radioactive dust for long-term storage or burial and device for its implementation |
CN110867269B (en) * | 2019-11-27 | 2021-12-03 | 中广核工程有限公司 | Spent fuel dry-type storage vertical storage module |
CN110867269A (en) * | 2019-11-27 | 2020-03-06 | 中广核工程有限公司 | Spent fuel dry-type storage vertical storage module |
Also Published As
Publication number | Publication date |
---|---|
ZA993676B (en) | 2000-11-30 |
AU4275099A (en) | 1999-12-20 |
WO1999063544A1 (en) | 1999-12-09 |
GB9811538D0 (en) | 1998-07-29 |
GB2337722B (en) | 2002-01-09 |
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