EP3607561B1 - Conteneur pour dechets radioactifs de faible a haute activite et a vie longue - Google Patents
Conteneur pour dechets radioactifs de faible a haute activite et a vie longue Download PDFInfo
- Publication number
- EP3607561B1 EP3607561B1 EP18715703.7A EP18715703A EP3607561B1 EP 3607561 B1 EP3607561 B1 EP 3607561B1 EP 18715703 A EP18715703 A EP 18715703A EP 3607561 B1 EP3607561 B1 EP 3607561B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- container
- steel
- wall
- radioactive waste
- waste
- 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.)
- Active
Links
- 239000002927 high level radioactive waste Substances 0.000 title 1
- 229910000831 Steel Inorganic materials 0.000 claims description 47
- 239000010959 steel Substances 0.000 claims description 47
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 32
- 239000002901 radioactive waste Substances 0.000 claims description 27
- 239000006004 Quartz sand Substances 0.000 claims description 24
- 229910001220 stainless steel Inorganic materials 0.000 claims description 9
- 239000000919 ceramic Substances 0.000 claims description 7
- 239000004033 plastic Substances 0.000 claims description 7
- 229920003023 plastic Polymers 0.000 claims description 7
- 239000010935 stainless steel Substances 0.000 claims description 7
- 239000002925 low-level radioactive waste Substances 0.000 claims description 3
- 239000011248 coating agent Substances 0.000 claims description 2
- 238000000576 coating method Methods 0.000 claims description 2
- 239000002699 waste material Substances 0.000 description 32
- 230000000694 effects Effects 0.000 description 28
- 238000003860 storage Methods 0.000 description 12
- 238000002844 melting Methods 0.000 description 11
- 230000008018 melting Effects 0.000 description 11
- 230000002285 radioactive effect Effects 0.000 description 10
- 230000005855 radiation Effects 0.000 description 9
- 230000007774 longterm Effects 0.000 description 6
- 239000004576 sand Substances 0.000 description 6
- 239000000126 substance Substances 0.000 description 6
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 5
- 229910052770 Uranium Inorganic materials 0.000 description 4
- 239000000543 intermediate Substances 0.000 description 4
- 238000007726 management method Methods 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 239000000203 mixture Substances 0.000 description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 230000015572 biosynthetic process Effects 0.000 description 2
- 231100000045 chemical toxicity Toxicity 0.000 description 2
- 230000003750 conditioning effect Effects 0.000 description 2
- 238000010790 dilution Methods 0.000 description 2
- 239000012895 dilution Substances 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000009377 nuclear transmutation Methods 0.000 description 2
- 229920000642 polymer Polymers 0.000 description 2
- 230000005258 radioactive decay Effects 0.000 description 2
- 239000002689 soil Substances 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- PNDPGZBMCMUPRI-HVTJNCQCSA-N 10043-66-0 Chemical compound [131I][131I] PNDPGZBMCMUPRI-HVTJNCQCSA-N 0.000 description 1
- OYEHPCDNVJXUIW-FTXFMUIASA-N 239Pu Chemical compound [239Pu] OYEHPCDNVJXUIW-FTXFMUIASA-N 0.000 description 1
- 229910000978 Pb alloy Inorganic materials 0.000 description 1
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 241000897276 Termes Species 0.000 description 1
- 241000863032 Trieres Species 0.000 description 1
- 229910052768 actinide Inorganic materials 0.000 description 1
- 150000001255 actinides Chemical class 0.000 description 1
- 229910052785 arsenic Inorganic materials 0.000 description 1
- RQNWIZPPADIBDY-UHFFFAOYSA-N arsenic atom Chemical compound [As] RQNWIZPPADIBDY-UHFFFAOYSA-N 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- TVFDJXOCXUVLDH-RNFDNDRNSA-N cesium-137 Chemical compound [137Cs] TVFDJXOCXUVLDH-RNFDNDRNSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000000295 complement effect Effects 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 230000001066 destructive effect Effects 0.000 description 1
- 230000008034 disappearance Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000004927 fusion Effects 0.000 description 1
- 239000011521 glass Substances 0.000 description 1
- 239000010438 granite Substances 0.000 description 1
- 239000002440 industrial waste Substances 0.000 description 1
- XEEYBQQBJWHFJM-UHFFFAOYSA-N iron Substances [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- UQSXHKLRYXJYBZ-UHFFFAOYSA-N iron oxide Inorganic materials [Fe]=O UQSXHKLRYXJYBZ-UHFFFAOYSA-N 0.000 description 1
- 235000013980 iron oxide Nutrition 0.000 description 1
- VBMVTYDPPZVILR-UHFFFAOYSA-N iron(2+);oxygen(2-) Chemical class [O-2].[Fe+2] VBMVTYDPPZVILR-UHFFFAOYSA-N 0.000 description 1
- 231100001231 less toxic Toxicity 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- QSHDDOUJBYECFT-UHFFFAOYSA-N mercury Chemical compound [Hg] QSHDDOUJBYECFT-UHFFFAOYSA-N 0.000 description 1
- 229910052753 mercury Inorganic materials 0.000 description 1
- 238000005065 mining Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 239000006223 plastic coating Substances 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- HZEBHPIOVYHPMT-BKFZFHPZSA-N polonium-214 atom Chemical compound [214Po] HZEBHPIOVYHPMT-BKFZFHPZSA-N 0.000 description 1
- 229920001296 polysiloxane Polymers 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 231100000336 radiotoxic Toxicity 0.000 description 1
- 230000001690 radiotoxic effect Effects 0.000 description 1
- 238000004064 recycling Methods 0.000 description 1
- 239000011435 rock Substances 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 239000000377 silicon dioxide Substances 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
- 231100000331 toxic Toxicity 0.000 description 1
- 230000002588 toxic effect Effects 0.000 description 1
- 231100000419 toxicity Toxicity 0.000 description 1
- 230000001988 toxicity Effects 0.000 description 1
- 230000001131 transforming effect Effects 0.000 description 1
- JFALSRSLKYAFGM-OIOBTWANSA-N uranium-235 Chemical compound [235U] JFALSRSLKYAFGM-OIOBTWANSA-N 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
Images
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
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
Definitions
- the present invention relates to the field of the storage of long-lived radioactive waste. More specifically, the present invention relates to a long-lived, low to high activity radioactive waste storage container.
- Radioactive waste is any radioactive material that can no longer be recycled or reused by humans.
- Nuclear waste comes from very diverse origins and natures. These are, for example, elements contained in the spent fuel of nuclear power plants, apart from the Uranium and Plutonium contained in the latter, radioactive elements for medical or industrial use, or materials brought into contact with radioactive elements.
- radioactive waste is low-level radioactive waste with a so-called short life.
- the choice and their management method were made several decades ago, by setting up surface storage centers on an industrial scale.
- the conditioning and long-term storage processes on the surface or underground the objective of which is to perfect the conditioning of radioactive waste and their long-term storage methods, while guaranteeing the protection of the people and the environment with solutions that complement those already in existence, making waste even more secure.
- the half-life does not depend on the mass of material considered.
- Each pure radionuclide has a perfectly known half-life, its value can range from less than a thousandth of a second (e.g. Polonium 214: 0.16ms) to several billion years (e.g. Uranium 238: 4.5 billion years) going through all values intermediates (Iodine 131: 5 days, Cesium 137: 30 years, Plutonium 239: 24,000 years, Uranium 235: 7 million years, etc.).
- the longest half-life of all the radionuclides present is taken as the value of the half-life.
- a radionuclide is transformed, by disintegration, into another nucleus called a “daughter product”; either this nucleus of filiation is stable, or it is also radioactive and disintegrates in its turn ... and so on until a stable nucleus is formed.
- a short-lived initial nucleus may well have long-lived daughter products. It is then the period of the latter that we retain.
- the classification according to the activity reflects the technical precautions that it is necessary to take in terms of radiation protection; the classification according to the period reflects the duration of the nuisance
- Radioisotopes will be all the more dangerous when they are highly radiotoxic, have chemical toxicity, and can easily pass into the environment.
- Radioactive waste which requires elaborate and specific protection measures is HAVL waste.
- the activity of these wastes is usually sufficient to cause burns if left exposed for too long.
- This HAVL waste mainly comes from spent fuel from nuclear power plants.
- HAVL waste "underground”, that is to say at depths, for example, not exceeding 5 m underground, and in supervised places, allows easy access to the waste. in the event of future recycling.
- Fire is an eminently destructive natural element, and the means of storing HAVL waste underground must be able to withstand it at least temporarily.
- the document WO 2011/026976 discloses a radioactive waste package comprising two layers covering the waste.
- the package comprises: an outer layer comprising a mixture of liquefied micronized plastics and a powder of micronized iron oxides; an internal layer of vitrified materials.
- the outer layer is 2-3mm.
- the outer layer has an adsorption capacity for rays coming from the outside.
- the package may also include an additional plastic coating for protection against water.
- the outer layer is resistant to radiation and heat, however it is certainly not resistant to ignition.
- Drums are also known and prevalent in the market in various forms. Drums often used for long-term storage are drums comprising a bottom, an outer wall and a cover, as well as means for closing the cover on the outer wall. An internal wall lead blocks some of the gamma radiation from the waste. However, such drums do not withstand high temperatures.
- An objective of the present invention is to increase the security of a radioactive waste container, more particularly to increase the resistance to high temperatures, with a view to its storage on the surface or in the basement and to the associated risk of fire. .
- a container for radioactive waste comprising a steel outer wall, a steel inner wall, a lead layer located between the two steel walls, a steel bottom, a steel cover, a volume of quartz sand located inside the container, at least one container / cassette / inner box coated / surrounded / covered at least partially by the volume of quartz sand and radioactive waste located inside the container.
- the container comprises, like the existing drums, an outer wall and a layer of lead. It is distinguished by an internal steel wall in contact on one side with the lead layer and on the other side with a layer of quartz sand, itself in contact with the wall of the container. Confining the lead in the space between the double steel wall ensures good radiation protection, even at temperatures above the melting point of lead.
- the layer of quartz sand and the layer of lead will strengthen the resistance to high temperatures and will ensure the integrity of the container even at very high temperatures.
- the lead layer and the quartz sand layer will increase the temperature resistance and ensure the integrity of the container even at very high temperatures for a while.
- Lead according to its purity has a melting point of about 320 ° C and a boiling point of the order of 1700 ° C. Quartz sands according to their purity have a melting point of 1300-1600 ° C and a boiling point of the order of 2000 ° C.
- the lead layer has a thickness of between 25 mm and 50 mm.
- the layer of quartz sand between the container and the internal steel wall preferably has a thickness of at least 2 cm, preferably at least 3 cm.
- the maximum thickness of the sand layer is preferably less than 10 cm, more preferably less than 8 cm and in particular less than 6 cm.
- the outer wall comprises a pressure relief valve.
- the valve will allow the evacuation of gases resulting from the melting / boiling of the lead contained in the space between the double steel wall.
- the inner container is preferably made of stainless steel.
- the stainless steel inner pot will not melt to a melting temperature of 1535 ° C.
- the stainless steel inner container may contain low level radioactive waste.
- the inner container is ceramic.
- the ceramic inner container is very interesting for its resistance to a temperature of 1400 ° C.
- the ceramic inner container may contain highly radioactive waste.
- the cover comprises an external steel wall, an internal steel wall and a lead layer contained between the two steel walls.
- the bottom comprises an outer wall of steel, an inner wall of steel and a layer of lead contained between the two walls of steel. The cover and, where appropriate, the bottom thus produced can block part of the gamma radiation of the waste.
- the inner container may include a removable cap.
- the inner container with the cap will fully isolate the radioactive waste.
- the container may comprise an interior rack with one or more compartments, the receptacle (s) being arranged in said interior rack.
- the rack facilitates the arrangement of several containers inside the container.
- the interior rack may include one or more doors giving easy access to the compartment (s).
- the interior rack preferably comprises one or more centering means and / or one or more gripping means. Furthermore, the interior rack may include one or more holes in order to allow the sand to fill the space between the containers and the rack.
- the steel is stainless steel, preferably steel of the 316L type.
- the composition of the stainless steels can alternatively be that of other stainless steels used in the nuclear industry or also in other industries, for example in the marine field or in the field of secure closures of a dwelling.
- the container further comprises a layer of plastics coating the radioactive waste in the inner container.
- the plastic layer blocks more of the radioactive radiation.
- the container preferably comprises an outer rubber casing covering the outer wall.
- the figure 1 illustrates a container 10 for radioactive waste according to a first embodiment of the invention.
- the radioactive waste container 10 comprises an outer wall 12 of steel, an inner wall 14 of steel, a lead layer 16 contained between the two steel walls 12 and 14, a bottom 18 of steel, a cover 20 of steel, a volume 22 of quartz sand located inside the container and at least one container / cassette / inner box 24 1 and 24 2 coated / surrounded / covered at least partially by the volume of quartz sand 22 (represented by crosses in the image).
- the radioactive waste 26 is located inside the container 24.
- bottom 18 and cover 20 of the container 10 By internal wall 14, bottom 18 and cover 20 of the container 10, it is meant that once the internal wall has been assembled, the bottom 18 and the cover 20 of the container form an internal envelope for isolating the waste 26.
- This internal envelope defines a interior space in which the receptacles 24 1 and 24 2 are housed with the waste 26 as well as the quartz sand 22.
- the steel bottom 18 is a wall receiving the container and the outer and inner walls 12 and 14 which extend from the bottom 18 to the cover 20, around the container 24 1 and 24 2 .
- the background forms a circular contour, it can alternatively form an oval, square or any polygonal contour.
- the walls external and internal peripherals and the cover can be of corresponding or different shape.
- the internal and external walls 12 and 14 can be produced, for example, by welding two preliminary rounded steel sheets.
- the inner and outer walls 12 and 14 are welded at their lower edge to the steel bottom 18.
- Lead or a preloaded lead alloy is then poured between the inner and outer walls to form the lead layer 16.
- the lead layer 16 does not spread inside the container.
- the bottom 18 may be flat or else comprise particular shapes, for example for the positioning of the receptacle (s) 24 1 and 24 2 .
- the outer wall has a circular section with an outer diameter of between 500 mm and 1000 mm.
- the container has a height between the bottom and the lid of between 800 mm and 1500 mm.
- the inner and outer walls 12 and 14 are between 3 mm and 10 mm thick and the lead layer 16 is between 25 mm and 50 mm thick.
- the steel bottom 18 and the steel cover can be of a thickness equal to more than twice, for example three times the value of the thickness of the internal and external walls 12 and 14.
- the container 10 comprises a circular ring 19 for fixing the cover 20 made of steel and attached to the upper end of the outer and inner walls 12 and 14.
- the fixing ring 19 includes holes for receiving cover fixing bolts passing through holes. corresponding holes on the steel cover 20.
- quartz sand silica sand with traces of different elements such as Al, Li, B, Fe, Mg, Ca, Ti, Rb, Na, OH. Quartz sand has the property of vitrifying after melting and then hardening. We will choose a quartz sand with a low melting point. The volume of glass thus formed can also block part of the radioactive radiation (for example with a preliminary mixture of the quartz sand with a material absorbing the radiations).
- the outer wall 12 comprises a pressure relief valve 40. In addition to the evacuation of the gases emanated in the event of melting of the layer 16 of lead.
- the container 10 further comprises a shelving means 50 or rack / display comprising one or more superimposed compartments 52 1 and 52 2 receiving the two containers 24 1 and 24 2 .
- the compartments each include a door (not shown) allowing easy access to the interior of the compartments.
- the interior rack 50 comprises a lower wall 53 in contact with the bottom 18 of the container 10, an upper wall 54, a cylindrical wall 56 extending between the lower and upper walls 53 and 54, as well as an intermediate wall 58 forming a bearing between the lower and upper walls 52 and 54.
- the first container 24 1 is arranged on the lower wall 52 of the interior rack 50.
- the second container 24 2 is placed on the intermediate wall 58.
- the side wall 56 comprises several holes or orifices 60.
- the interior rack 50 is placed inside the container before the quartz sand.
- the holes 60 in the side wall 56 of the interior rack 50 allow the passage of quartz sand into the compartments 52 1 and 52 1 to surround and call the containers 24 1 and 24 2 .
- the sand can also cover the receptacles 24 1 and 24 2 . It should be noted that the sand could also first be deposited under the receptacle 24 1 .
- the interior rack 50 may include vertical / horizontal / diagonal uprights, and trays connected to the uprights; the quartz sand can thus surround / coat the containers while passing through the uprights and the trays.
- the interior rack 50 is made of stainless steel.
- the interior rack 50 comprises a second upper wall 54 'and a lead plate 70 disposed between the two upper walls 54 and 54'.
- the inner receptacles 24 1 and 24 2 comprise a removable cap 28 1 and 28 2 as well as connecting means / flange (s) / clips / screws 30 1 and 30 2 of the removable cap to the receptacle 24 1 and 24 2 .
- the inner receptacles 24 1 and 24 2 comprise centering means and / or one or more gripping means / hook / eyelet (not shown), for example on the cover 20.
- the container 10 comprises two interior receptacles 24 1 and 24 2 made of ceramic, preferably of ceramic of the ACA 997 type, more preferably of special ceramic ACS 99,8LS 172.
- the receptacle 24 1 and 24 2 with its cap 28 1 and 28 2 is between 250 mm and 300 mm high.
- the container 24 1 and 24 2 has a capacity of between 10 L and 20 L and withstands temperatures up to 1400 ° C.
- the waste 26 placed in the container 24 1 and 24 2 is highly radioactive.
- this embodiment is intended for the storage of long-lived medium and high activity radioactive waste, and in particular non-recoverable final waste which contains fission products and minor actinides, nuclear fuel ash.
- the container 10 further comprises a rubber / plastic / silicone outer casing 80 covering the outer wall 12.
- the outer rubber casing 80 is partially shown in the picture at the lower area of the container 10.
- the container 10 is partially shown in the picture.
- Outer rubber casing 80 is made by immersing the container 10 in a bath of liquefied rubber. The outer casing 80 will prevent degradation of the container by water.
- the figure 2 illustrates a second embodiment of the container 10 seen in relation to the figure 1 . They will have in common the characteristics described in relation to the first embodiment of the figure 1 .
- the reference numbers of the figure 2 are used at the figure 1 for the corresponding elements, these numbers being however increased by 100 for the second embodiment illustrated in figure 2 .
- Specific reference numbers are used for a specific item, these numbers ranging from 100 to 200.
- the container comprises a single inner container 124.
- the inner container 124 is placed in a single compartment 152 of the inner rack 150.
- the inner container 124 is made of stainless steel.
- the inner container 124 with its cap 128 is between 500 mm and 1000 mm high.
- the inner container 124 has a capacity of between 50 L and 350 L.
- the waste 126 located in the inner container 124 is weakly radioactive.
- the wastes are metallic structures of the fuel elements, resulting from the operation of the reactor, used gloves, protective suits, irradiated tools, shells, end caps, radioactive mining residues that can pose problems of chemical toxicity if the uranium is present with other otherwise toxic products such as lead, arsenic, mercury etc ..., radioactive waste from the medical sector and whose half-life is less than 100 days.
- the container 100 also comprises a layer of plastic 190, preferably a low density polymer, covering the radioactive waste in the inner container 124.
- the plastic can be liquefied beforehand and mixed with a load. and / or come from several low / high density polymers.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Packages (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
LU100166A LU100166B1 (fr) | 2017-04-07 | 2017-04-07 | Conteneur pour déchets radioactifs de faible à haute activité et à vie longue |
PCT/EP2018/058753 WO2018185233A1 (fr) | 2017-04-07 | 2018-04-05 | Conteneur pour dechets radioactifs de faible a haute activite et a vie longue |
Publications (2)
Publication Number | Publication Date |
---|---|
EP3607561A1 EP3607561A1 (fr) | 2020-02-12 |
EP3607561B1 true EP3607561B1 (fr) | 2021-03-03 |
Family
ID=59021556
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP18715703.7A Active EP3607561B1 (fr) | 2017-04-07 | 2018-04-05 | Conteneur pour dechets radioactifs de faible a haute activite et a vie longue |
Country Status (7)
Country | Link |
---|---|
US (1) | US11367538B2 (ru) |
EP (1) | EP3607561B1 (ru) |
CN (1) | CN110709944A (ru) |
CA (1) | CA3058277A1 (ru) |
EA (1) | EA037732B1 (ru) |
LU (1) | LU100166B1 (ru) |
WO (1) | WO2018185233A1 (ru) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
LU502319B1 (en) | 2022-06-20 | 2023-12-20 | Global Tele Marketing Gtm Sa | Radiation and impact-protected radioactive waste cask |
Family Cites Families (20)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1500850A (fr) * | 1966-06-10 | 1967-11-10 | Commissariat Energie Atomique | Récipient de transport d'effluents radioactifs |
FR1568340A (ru) * | 1968-03-29 | 1969-05-23 | ||
US3754141A (en) * | 1972-07-12 | 1973-08-21 | Atomic Energy Commission | Shipping and storage container for high power density radioactive materials |
GB2020626B (en) * | 1978-05-15 | 1982-12-15 | Hitachi Shipbuilding Eng Co | Bag for enclosing a cask |
HU179174B (en) * | 1979-09-14 | 1982-08-28 | Eroemue Es Halozattervezoe | Process and apparatus for transferring and housing radioactive and/or other dangerous materials |
US4666659A (en) * | 1983-10-25 | 1987-05-19 | Mitsubishi Heavy Industries, Ltd. | Shipping and storage container for spent nuclear fuel |
US4535250A (en) * | 1984-05-30 | 1985-08-13 | The United States Of America As Represented By The United States Department Of Energy | Container for radioactive materials |
US4935943A (en) * | 1984-08-30 | 1990-06-19 | The United States Of America As Represented By The United States Department Of Energy | Corrosion resistant storage container for radioactive material |
US6489623B1 (en) * | 2000-11-07 | 2002-12-03 | Global Nuclear Fuel -- Americas, Llc | Shipping container for radioactive materials and methods of fabrication |
JP2006275730A (ja) * | 2005-03-29 | 2006-10-12 | Mitsui Eng & Shipbuild Co Ltd | キャスクの構造 |
EP2041753B1 (en) * | 2006-06-30 | 2013-10-09 | Holtec International, Inc. | Apparatus, system and method for storing high level waste |
FR2925975B1 (fr) * | 2007-12-26 | 2016-05-27 | Areva Np | Conteneur de transport pour assemblage de combustible nucleaire, et procede de transport d'un assemblage de combustible nucleaire |
WO2010129372A2 (en) * | 2009-04-28 | 2010-11-11 | Holtec International, Inc. | Cask apparatus, system and method for transporting and/or storing high level waste |
LU91605B1 (fr) | 2009-09-07 | 2011-03-08 | Terra Nobilis S A | Procédé de sécurisation du stockage de déchets radioactifs de longue vie. |
CN201904094U (zh) * | 2010-11-19 | 2011-07-20 | 成都中核高通同位素股份有限公司 | γ刀放射源运输容器 |
US9018432B2 (en) * | 2012-10-25 | 2015-04-28 | Barnhardt Manufacturing Company | Processing radioactive waste for shipment and storage |
US9865366B2 (en) * | 2014-07-10 | 2018-01-09 | Energysolutions, Llc | Shielded packaging system for radioactive waste |
CN104575648B (zh) * | 2014-12-24 | 2017-05-03 | 中国原子能科学研究院 | 一种用于快堆mox燃料组件的运输容器 |
CN107533873B (zh) * | 2015-05-04 | 2019-07-30 | 霍尔泰克国际公司 | 用于乏核燃料的燃料篮及其实施容器 |
US10878972B2 (en) * | 2019-02-21 | 2020-12-29 | Deep Isolation, Inc. | Hazardous material repository systems and methods |
-
2017
- 2017-04-07 LU LU100166A patent/LU100166B1/fr active IP Right Grant
-
2018
- 2018-04-05 US US16/603,414 patent/US11367538B2/en active Active
- 2018-04-05 EP EP18715703.7A patent/EP3607561B1/fr active Active
- 2018-04-05 CN CN201880033152.8A patent/CN110709944A/zh active Pending
- 2018-04-05 WO PCT/EP2018/058753 patent/WO2018185233A1/fr active Application Filing
- 2018-04-05 EA EA201992292A patent/EA037732B1/ru unknown
- 2018-04-05 CA CA3058277A patent/CA3058277A1/fr active Pending
Non-Patent Citations (1)
Title |
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None * |
Also Published As
Publication number | Publication date |
---|---|
WO2018185233A1 (fr) | 2018-10-11 |
US11367538B2 (en) | 2022-06-21 |
EP3607561A1 (fr) | 2020-02-12 |
EA037732B1 (ru) | 2021-05-14 |
CA3058277A1 (fr) | 2018-10-11 |
LU100166B1 (fr) | 2018-10-15 |
EA201992292A1 (ru) | 2020-02-25 |
CN110709944A (zh) | 2020-01-17 |
US20200043619A1 (en) | 2020-02-06 |
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