WO2011028165A1 - Method for long term deposit - Google Patents
Method for long term deposit Download PDFInfo
- Publication number
- WO2011028165A1 WO2011028165A1 PCT/SE2010/050921 SE2010050921W WO2011028165A1 WO 2011028165 A1 WO2011028165 A1 WO 2011028165A1 SE 2010050921 W SE2010050921 W SE 2010050921W WO 2011028165 A1 WO2011028165 A1 WO 2011028165A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- canister
- storage space
- water
- buffer material
- nuclear fuel
- Prior art date
Links
- 238000000034 method Methods 0.000 title claims abstract description 45
- 230000007774 longterm Effects 0.000 title claims abstract description 14
- 239000000463 material Substances 0.000 claims abstract description 41
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 31
- 239000004927 clay Substances 0.000 claims abstract description 17
- 239000003673 groundwater Substances 0.000 claims abstract description 14
- 239000002915 spent fuel radioactive waste Substances 0.000 claims abstract description 14
- 229920006395 saturated elastomer Polymers 0.000 claims abstract description 13
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims abstract description 10
- 229910000278 bentonite Inorganic materials 0.000 claims abstract description 10
- 239000000440 bentonite Substances 0.000 claims abstract description 10
- SVPXDRXYRYOSEX-UHFFFAOYSA-N bentoquatam Chemical compound O.O=[Si]=O.O=[Al]O[Al]=O SVPXDRXYRYOSEX-UHFFFAOYSA-N 0.000 claims abstract description 10
- 239000006004 Quartz sand Substances 0.000 claims abstract description 5
- 239000004576 sand Substances 0.000 claims abstract description 5
- 230000008021 deposition Effects 0.000 claims description 19
- 229910052751 metal Inorganic materials 0.000 claims description 14
- 239000002184 metal Substances 0.000 claims description 14
- 239000011435 rock Substances 0.000 claims description 11
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 claims description 8
- 229910052802 copper Inorganic materials 0.000 claims description 8
- 239000010949 copper Substances 0.000 claims description 8
- 150000002739 metals Chemical class 0.000 claims description 8
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 claims description 3
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 claims description 3
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 3
- 229910045601 alloy Inorganic materials 0.000 claims description 3
- 239000000956 alloy Substances 0.000 claims description 3
- 229910052804 chromium Inorganic materials 0.000 claims description 3
- 239000011651 chromium Substances 0.000 claims description 3
- 239000010936 titanium Substances 0.000 claims description 3
- 229910052719 titanium Inorganic materials 0.000 claims description 3
- 229910052726 zirconium Inorganic materials 0.000 claims description 3
- 238000005260 corrosion Methods 0.000 description 20
- 230000007797 corrosion Effects 0.000 description 20
- 239000010410 layer Substances 0.000 description 8
- 239000003758 nuclear fuel Substances 0.000 description 8
- 239000012857 radioactive material Substances 0.000 description 5
- 239000007788 liquid Substances 0.000 description 4
- 230000002285 radioactive effect Effects 0.000 description 4
- 239000002245 particle Substances 0.000 description 3
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000008020 evaporation Effects 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 239000001301 oxygen Substances 0.000 description 2
- 229910052760 oxygen Inorganic materials 0.000 description 2
- 150000003839 salts Chemical class 0.000 description 2
- 229910001018 Cast iron Inorganic materials 0.000 description 1
- 229910001208 Crucible steel Inorganic materials 0.000 description 1
- MYMOFIZGZYHOMD-UHFFFAOYSA-N Dioxygen Chemical compound O=O MYMOFIZGZYHOMD-UHFFFAOYSA-N 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 150000003842 bromide salts Chemical class 0.000 description 1
- 150000004649 carbonic acid derivatives Chemical class 0.000 description 1
- 238000005266 casting Methods 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 150000003841 chloride salts Chemical class 0.000 description 1
- 239000002734 clay mineral Substances 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 229910001882 dioxygen Inorganic materials 0.000 description 1
- 238000005538 encapsulation Methods 0.000 description 1
- -1 for example Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 229910052500 inorganic mineral Inorganic materials 0.000 description 1
- 239000011707 mineral Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000008239 natural water Substances 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 239000011241 protective layer Substances 0.000 description 1
- 238000009738 saturating Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 150000003568 thioethers Chemical class 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
- G21F9/22—Disposal of liquid waste by storage in a tank or other container
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
- G21F9/24—Disposal of liquid waste by storage in the ground; by storage under water, e.g. in ocean
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
Definitions
- a buffer material such as clay, for example bentonite clay, and/or sand, for example quartz sand.
- the Swedish Nuclear Fuel and Waste Management Co has developed the KBS-3 concept that is based on encapsulation of spent nuclear fuel in a protective copper casing that is thereafter embedded in bentonite clay in deposition holes situated at a few meters distance from each other in a system of horizontal tunnels at a depth of 400-700 meters below the ground surface.
- Bentonite clay has properties causing it to form an efficient buffer between rock and canister, and will, inter alia, protect the canister against smaller rock movements and form a barrier against radioactive species spreading from a canister that is not impermeable.
- the tunnels are filled with backfill material such as, for example, clay and crushed rock.
- backfill material such as, for example, clay and crushed rock.
- the ground water then slowly seeps into the deposition holes. Initially, the voids between the clay mineral particles are filled with water and, subsequently, the water is drawn in between the mineral flakes.
- the bentonite clay gets wet, it swells and fills the cavities and cracks surrounding the deposition hole.
- the natural saturation process can take up to a hundred years, or even longer, depending on the properties of the rock. According to a recent decision, the planned final repository in Sweden will be placed at a location with bedrock considered to have few cracks and very slow rate of water movement.
- the canister with the nuclear fuel is intended to last for very long periods of time, at least 100 000 years, and it is therefore important that the corrosion is kept as low as possible.
- Another corrosion process that may affect the heated metal canister is evaporation- induced corrosion.
- Ground water entering from cracks in the rock reaches the hot canister surface and evaporates, which can result in an accumulation of aggressive salts (chlorides, sulphides, bromides, carbonates, etc.) from the ground water on the metal surface of the canister.
- aggressive salts chlorides, sulphides, bromides, carbonates, etc.
- Corrosion damages caused by said processes could lead to destroyed copper canisters, and thus, in the worst case, to leakage of radioactive particles within a very near future, long before the radioactivity has abated to a harmless level.
- the, properties of the clay can be destroyed if it is heated and dried for prolonged periods of time. Bentonite clay with degraded properties would not constitute a sufficiently efficient barrier against radioactive leakage from a canister.
- the object of the present invention is therefore to achieve an improved method for the long-term storage that results in reduced corrosion of the canisters with nuclear fuel.
- this object is achieved in that the method further comprises the step of:
- the canister comprises an insert containing said spent nuclear fuel, and a copper casing that encloses the insert.
- a canister can be the one developed in accordance with the KBS-3 method of SKB.
- the canister comprises at least one additional casing/layer that encloses the copper casing and that consists of a passive film-forming metal or alloy, wherein the passive film on the casing is constituted by an essentially oxidic film that is rich in one or more of the metals belonging to the group of metals consisting of the metals zirconium, chromium and titanium.
- This additional casing/layer is primarily intended to protect the canister during the period when the temperature of the canister is elevated in accordance with what has been described in SE 531261 C2.
- the storage place is located at least 50 meters below the ground water surface, preferably at least 100 meters below the ground surface, more preferably at least 300 meters below the ground surface.
- the storage space is actively saturated with water to a level such that the entire canister is covered. Since the entire canister is "flooded", the corrosion problems of the canister caused by boundary layer corrosion, evaporation-induced corrosion, and atmospheric corrosion are minimized.
- the storage spaces are arranged as substantially vertical deposition holes at the bottom of a tunnel or a rock chamber, wherein the respective deposition holes are adapted in size to allow a canister to be arranged vertically therein, surrounded by the buffer material.
- KBS-3V has been described by SKB.
- the storage space can be constituted of one or several substantially horizontal deposition holes in the side wall of a tunnel or a rock chamber, wherein the respective deposition hole is adapted in size to allow at least one canister to be arranged horizontally therein, surrounded by the buffer material.
- horizontal deposition holes are used, it is conceivable that several canisters are placed in one deposition hole, so that they lie on a line.
- KBS-3H has been described by SKB. It is also conceivable to mix horizontal and vertical storage spaces.
- the respective storage space with an embedded canister is actively saturated with water so that a level of water saturation exceeding the highest point of the canister is reached after a period of time shorter than 5 years, more preferably after a period of time shorter than 1 year, even more preferably within a period of time shorter than 1 week.
- a more rapid process of water saturation reduces the period during which the canister risks being subjected to boundary layer corrosion, evaporation-induced corrosion, and atmospheric corrosion, which is of course advantageous.
- the invention also pertains to a device for long-term storage, containing at least one canister that contains spent nuclear fuel, arranged in a storage space located below the ground water level, embedded in a buffer material, and actively saturated with water to such a level that the entire canister has been covered in accordance with the method of any one of the foregoing claims.
- Fig. 1 shows a perspective view of a canister for the storage of a radioactive material
- Fig. 2 shows a schematic view of an underground tunnel system for the storage of radioactive material
- Fig. 3 shows a perspective close-up view of a tunnel with storage spaces, as taken from the circle I in Fig. 2; and Fig. 4 is a cross-sectional view of a storage space containing a canister and backfill material in accordance with the invention.
- Fig. 1 shows a preferred embodiment of a canister 1 intended for containment of a radioactive material, such as a spent nuclear fuel, for long-term storage.
- the canister 1 comprises a casing 2 that is substantially cylindrical with an opening at an upper short end 2a, and has an insert 3 that preferably has a number of longitudinal cavities intended for spent fuel rods, and a cover 4 that can be attached to the upper short end 2a of the casing 2 in order to seal the canister.
- the casing 2 and the cover 4 are made of metal.
- the casing 2 can consist of five centimetres thick copper in accordance with the KBS-3 method of SKB
- the insert 3 can, for example, be made of cast iron, as is suggested in the KBS-3 method, or cast steel.
- the length of the canister 1 is preferably in the range of 3-7 m and its diameter in the range of 0.5-2 m, but it will be appreciated that also other dimensions can be used and that the invention is not limited thereto.
- Fig. 2 shows a schematic representation of the appearance of an underground storage 10 intended for long-term storage of the radioactive material, comprising a plurality of tunnels 1 1 which have been formed in the bedrock at a depth below the ground water level 20, at least 200 m, but preferably at least 400 m below the ground surface 22.
- Each of the tunnels 1 1 contain a plurality of storage spaces 12 intended for a canister 1 , and these tunnels 11 are connected through a connecting passage 14 to each other and to a connecting passage 13 to the ground surface which, at the ground surface 22, opens into a facility 21, from where the transport of canisters 1 containing nuclear fuel to a storage space 12 can be initiated via channels and tunnels 13, 14, 1 1.
- Fig. 3 shows an enlargement of the circle I in Fig. 2, wherein a perspective view of a tunnel 1 1 having a plurality of storage spaces 12 can be seen.
- These storage spaces 12 are designed as vertical deposition holes at the bottom of the tunnels 1 1 , and are each so large that a canister 1 and a surrounding backfill material 5 can be placed in the storage space 12 such as, for example, proposed by SKB in the KBS-3V method.
- the canisters can be stored in horizontal deposition holes such as, for example, proposed by SKB in the KBS-3H method.
- a cross-section of such a storage space 12 and tunnel 1 1 , with a canister 1 placed in the storage space 12, can be seen in Fig. 4.
- a backfill material in the form of a buffer material 5, such as clay and/or sand, preferably a bentonite clay or quartz sand, or a mixture thereof, is placed in the gap remaining between the canister 1 and the limiting surfaces of the storage space 12.
- a backfill material 6 is used to fill up the rest of the tunnel 11 so that it is sealed.
- a suitable quantity of a nuclear fuel is placed in the insert 3 of a casing 2, whereupon the casing is sealed by a cover 4 that is attached to the upper surface 2a, so that a canister 1 is formed.
- a cover 4 that is attached to the upper surface 2a, so that a canister 1 is formed.
- suitable also other substances or materials can be contained in the canister, such as additional backfill material or other types of radioactive material.
- the canister 1 In order to bring the canister 1 to a storage space 12 intended therefore, in one of the tunnels 1 1 , the canister is transported from the ground surface 22 down through the connecting passage 13, along the connecting passage 14 and out into the selected tunnel 1 1. Now, the canister 1 is positioned in a storage space 12 that is either completely empty or already contains a quantity of the buffer material 5. After the positioning, an additional amount of the buffer material 5 is added, if necessary, until the canister 1 is enclosed by this material to a desired degree. Preferably, the canister 1 is completely covered by this material 5, so that no part of the surface of the canister 1 is in direct contact with the limiting surfaces of the storage space 12. Thereupon, a liquid, such as water, is added to the buffer material 5, so that it is actively saturated with water.
- a liquid such as water
- This active saturation occurs more rapidly than if ground water could seep into the storage space 12 through cracks in the bedrock, and it is advantageous to avoid a situation where some part of the canister 1 is in contact with a liquid surface, such as a water surface, so that one part of the canister is above the liquid and another part is submerged therein for any prolonged periods of time.
- a liquid surface such as a water surface
- the fact is that such a situation may result in a relatively strong degradation of the casing 2 at the point where the liquid surface is, so that there is a risk of such serious damages being caused that a connection is formed between the contained nuclear fuel and the surrounding environment as time goes on.
- Such a process also may be accelerated in that the casing 2 is heated by reactions in the contained nuclear fuel, wherein the activity of the spent nuclear fuel may imply that the casing 2 has a temperature in the range of 50-90 °C for hundreds of years. It is therefore very advantageous to accelerate the water saturation of the storage space 12 so that the entire canister 1 embedded into the buffer material 5 is covered more rapidly than what would have occurred with only natural water saturation. After having saturated the storage space 12 with the embedded canister 1, it can optionally be sealed up, for example by casting a cover of concrete.
- a backfill material 6 can then be used to fill up the tunnel 1 1 so that the canisters 1 can be additionally protected against influence from the outside. It is of course conceivable that a tunnel 11 is left unfilled, in order to make it easier to access the storage spaces.
- the backfill material 6 can be constituted of clay (for example bentonite clay), sand (for example quartz sand), gravel, rock fill, excavated material, etc. and, the tunnel 1 1 can be sealed up, if desired.
- the invention is not limited by what has been described above, but can be varied within the scope of the following claims.
- other designs of storage spaces and systems of tunnels therebetween can be used for storing canisters with nuclear fuel
- the design and constituent materials of a canister are not a focus of the invention, but they can be varied depending on what is suitable for the case in question.
- SE425707 and US4834917, SE 509177, US4562001 ⁇ show further examples of canister configurations.
- the buffer material is, of course, not limited to bentonite clay, but different materials can be used for the containment of a canister.
Landscapes
- Engineering & Computer Science (AREA)
- Environmental & Geological Engineering (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
- Biodiversity & Conservation Biology (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Ocean & Marine Engineering (AREA)
- Oceanography (AREA)
- Sustainable Development (AREA)
- Filling Or Discharging Of Gas Storage Vessels (AREA)
- Underground Structures, Protecting, Testing And Restoring Foundations (AREA)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
EP10814026.0A EP2474002A4 (en) | 2009-09-01 | 2010-08-27 | LONG-TERM STORAGE PROCESS |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
SE0950626-2 | 2009-09-01 | ||
SE0950626A SE534094C2 (sv) | 2009-09-01 | 2009-09-01 | Metod vid långtidsförvar |
Publications (1)
Publication Number | Publication Date |
---|---|
WO2011028165A1 true WO2011028165A1 (en) | 2011-03-10 |
Family
ID=43649519
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/SE2010/050921 WO2011028165A1 (en) | 2009-09-01 | 2010-08-27 | Method for long term deposit |
Country Status (3)
Country | Link |
---|---|
EP (1) | EP2474002A4 (sv) |
SE (1) | SE534094C2 (sv) |
WO (1) | WO2011028165A1 (sv) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2016130671A (ja) * | 2015-01-13 | 2016-07-21 | 清水建設株式会社 | ベントナイト成形体の乾燥方法 |
JP2016217028A (ja) * | 2015-05-21 | 2016-12-22 | 清水建設株式会社 | 吸水膨張性粘土の充てん方法および構築物 |
CN108461170A (zh) * | 2018-04-24 | 2018-08-28 | 海南大学 | 一种新型高放废物深地质处置缓冲材料及其施工方法 |
JP2018188804A (ja) * | 2017-04-28 | 2018-11-29 | 清水建設株式会社 | 遮水材料およびその製造方法、廃棄物貯蔵施設およびその構築方法 |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007319732A (ja) * | 2006-05-30 | 2007-12-13 | Shimizu Corp | 隙間充填材及び遮水方法 |
SE531261C2 (sv) * | 2007-05-25 | 2009-02-03 | Olle Grinder | Kapsel avsedd för slutförvaring av utbränt kärnbränsle |
Family Cites Families (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5171483A (en) * | 1991-05-16 | 1992-12-15 | Science Applications International Corporation | Method for retrievable/permanent storage of hazardous waste materials |
US8470406B2 (en) * | 2005-08-19 | 2013-06-25 | Kajima Corporation | Method of spray application, and spray apparatus, for bentonite material |
-
2009
- 2009-09-01 SE SE0950626A patent/SE534094C2/sv not_active IP Right Cessation
-
2010
- 2010-08-27 EP EP10814026.0A patent/EP2474002A4/en not_active Withdrawn
- 2010-08-27 WO PCT/SE2010/050921 patent/WO2011028165A1/en active Application Filing
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007319732A (ja) * | 2006-05-30 | 2007-12-13 | Shimizu Corp | 隙間充填材及び遮水方法 |
SE531261C2 (sv) * | 2007-05-25 | 2009-02-03 | Olle Grinder | Kapsel avsedd för slutförvaring av utbränt kärnbränsle |
Non-Patent Citations (3)
Title |
---|
BENNETT D.G. ET AL: "Overview of European concepts for high-level waste and spent fuel disposal with special reference waste container corrosion", INGAR I JOURNAL OF NUCLEAR MATERIALS, vol. 379, no. 1-3, 30 September 2008 (2008-09-30), XP025410041 * |
F. KING ET AL: "Copper corrosion under expected conditions in a deep geological repository", TR-01-23, 2001, XP008161581, Retrieved from the Internet <URL:http://www.skb.se/upload/publications/pdf/TR-01-23webb.pdf> * |
See also references of EP2474002A4 * |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2016130671A (ja) * | 2015-01-13 | 2016-07-21 | 清水建設株式会社 | ベントナイト成形体の乾燥方法 |
JP2016217028A (ja) * | 2015-05-21 | 2016-12-22 | 清水建設株式会社 | 吸水膨張性粘土の充てん方法および構築物 |
JP2018188804A (ja) * | 2017-04-28 | 2018-11-29 | 清水建設株式会社 | 遮水材料およびその製造方法、廃棄物貯蔵施設およびその構築方法 |
CN108461170A (zh) * | 2018-04-24 | 2018-08-28 | 海南大学 | 一种新型高放废物深地质处置缓冲材料及其施工方法 |
Also Published As
Publication number | Publication date |
---|---|
EP2474002A1 (en) | 2012-07-11 |
SE0950626A1 (sv) | 2011-03-02 |
EP2474002A4 (en) | 2016-03-30 |
SE534094C2 (sv) | 2011-04-26 |
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