WO2021119557A2 - Passive heat removal casks and methods of using the same - Google Patents
Passive heat removal casks and methods of using the same Download PDFInfo
- Publication number
- WO2021119557A2 WO2021119557A2 PCT/US2020/064713 US2020064713W WO2021119557A2 WO 2021119557 A2 WO2021119557 A2 WO 2021119557A2 US 2020064713 W US2020064713 W US 2020064713W WO 2021119557 A2 WO2021119557 A2 WO 2021119557A2
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- cask
- heat
- transport path
- cavity
- shielding
- Prior art date
Links
- 238000000034 method Methods 0.000 title claims description 12
- 230000005855 radiation Effects 0.000 claims abstract description 14
- 239000012530 fluid Substances 0.000 claims abstract description 7
- 238000012546 transfer Methods 0.000 claims description 19
- 238000010438 heat treatment Methods 0.000 claims description 9
- 239000000446 fuel Substances 0.000 claims description 8
- 239000007787 solid Substances 0.000 claims description 6
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 6
- 239000003758 nuclear fuel Substances 0.000 claims description 4
- 239000011824 nuclear material Substances 0.000 claims description 4
- 239000002699 waste material Substances 0.000 claims description 4
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims description 2
- 230000003213 activating effect Effects 0.000 claims description 2
- 230000005865 ionizing radiation Effects 0.000 claims 3
- 229910052751 metal Inorganic materials 0.000 claims 1
- 239000002184 metal Substances 0.000 claims 1
- 229910052708 sodium Inorganic materials 0.000 claims 1
- 239000011734 sodium Substances 0.000 claims 1
- 239000000463 material Substances 0.000 abstract description 16
- 238000007654 immersion Methods 0.000 description 5
- 230000000712 assembly Effects 0.000 description 4
- 238000000429 assembly Methods 0.000 description 4
- 238000001816 cooling Methods 0.000 description 4
- 238000003780 insertion Methods 0.000 description 3
- 230000037431 insertion Effects 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- 229910052580 B4C Inorganic materials 0.000 description 2
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 2
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 2
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 2
- 238000004891 communication Methods 0.000 description 2
- 239000001307 helium Substances 0.000 description 2
- 229910052734 helium Inorganic materials 0.000 description 2
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 229910001338 liquidmetal Inorganic materials 0.000 description 2
- 239000003607 modifier Substances 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000011800 void material Substances 0.000 description 2
- 229910000838 Al alloy Inorganic materials 0.000 description 1
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 1
- 229910000990 Ni alloy Inorganic materials 0.000 description 1
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 239000006096 absorbing agent Substances 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- PMHQVHHXPFUNSP-UHFFFAOYSA-M copper(1+);methylsulfanylmethane;bromide Chemical compound Br[Cu].CSC PMHQVHHXPFUNSP-UHFFFAOYSA-M 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 239000000945 filler Substances 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 150000001247 metal acetylides Chemical class 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 229910010271 silicon carbide Inorganic materials 0.000 description 1
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 description 1
- 229910052721 tungsten Inorganic materials 0.000 description 1
- 239000010937 tungsten Substances 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 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
- 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
-
- 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
-
- 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
Definitions
- FIG. 1 A is a cross-section of a related art transfer cask 10 used for storing heat generating waste, including radioactive materials like spent nuclear fuel and irradiated waste.
- cask 10 includes inner shielding 11 and outer shielding 12 that define a central open space into which fuel assembly 1 and handling basket 2 may be inserted and stored.
- Inner shielding 11 may be depleted uranium that maintains structural containment and blocks radiation emitted by contents of cask 10.
- Outer shielding 12 may be a thicker boron carbide jacket that provides further impact shielding and particularly neutron radiation shielding.
- FIG. 1C is a cross-section of related-art cask 10 at elevation line hi, showing inner shielding 11 as a ring jacketed by outer shielding 12.
- Several reinforcing dividers 15A, 15B, and 15C which may be high-strength stainless steel, divide and reinforce the shielding and form an outer surface of cask 10.
- Void 13 at a top of cask 10 may connect up to bi-stem assembly 20 at the top end of cask 10.
- Active pumps and fluid recirculators may connects through bi-stem assembly 20 into void 13 to actively cool and move heat away from contents of cask 10.
- bi-stem assembly 20 may allow for handling of cask 10, such as through a crane or other connection to assembly 20.
- cask 10 With proper ambient conditions and active cooling provided to cask 10, high-energy contents that generate large amounts of heat through radiation may be stored and transported for long periods of time without damaging cask 10 or irradiating the environment.
- US Patent Publication 2014/0177775 published June 26, 2014 Loewen et al. describes another related art cask for spent nuclear fuel with active cooling devices to also dissipate cask heat and is incorporated by reference herein in its entirety.
- Example embodiments include casks that passively rid themselves of heat that may be generated by their contents, with shielding around the contents to stop alpha, beta, gamma, or neutron radiation from leaking to the surrounding environment and one or more heat transport paths that allow the heat to easily move from inside the cask and shielding to outside the cask and ultimately into the environment or an external heat sink.
- the transport path may be any structure with high heat convection, conduction, and/or radiation, sufficient to prevent internal temperatures from reaching damaging temperatures, including heat pipes and conductive rods.
- the heat transport path may be bent or otherwise provide no straight line from inside to outside the cask, so that radiation travelling along such a line always hits shielding.
- An openable and closeable damper may surround an end of the heat transport path to control fluid convection about the heat transport path and ultimately heat loss from the cask.
- a jacket of fluid or meltable material that conducts heat by convection may surround the stored materials ensure an even temperature within the cask.
- the heat transport path and/or a heating element may be in communication with the jacket to cool and/or heat the jacket as desired.
- Example embodiment casks are useable to store, transport, and dispose of any sensitive or heat-generating material without damaging buildup of heat or irradiation. This may include radioactive waste, irradiated components, spent or fresh nuclear fuel, etc. Casks may be opened or closed to simultaneously load and offload materials at a consistent operating temperature provided by heaters in the cask. Several fuel assemblies and other highly radioactive structures can be placed and stored in casks without risk of melting or loss of containment due to the passive heat removal from the cask.
- FIG. 1A is a cross-section of a related art fuel transport cask.
- FIG. IB is a cross-section of the cask of FIG. 1A.
- FIG. 1C is another cross-section of the cask of FIG. 1A.
- FIG. 2A is a profile cross-section of an example embodiment example transfer cask.
- FIG. 2B is a detail of the heat transport path of the cask of FIG. 2A.
- FIG. 2C is a cross-section of the cask of FIG. 2A
- a "heat transport path” is a solid structure transferring heat at a high rate, higher than surrounding materials, without outside power or driven solid components, including conductive rods and heat pipes.
- FIG. 2A is a profile cross-section of an example embodiment heat transfer cask 100 using a heat transport path that passively removes heat from the contents of the cask.
- Cask 100 may have some similar configurations to related art casks discussed above or shown in FIGS. 1 A-C, with heat transport elements added as described below and structural and shielding elements made of strong, non-reactive materials.
- Example embodiment heat transfer cask 100 is robust and seals with the integrity of containment, and, as such is useable to store, transport, and dispose of dangerous or sensitive material, including radioactive components and nuclear material, without risk of leakage, reaction, or damage when exposed to force or harsh environments.
- heat transport path 150 directly connects an inner portion of cask 100 to an exterior or near exterior, to carry heat directly away from cask 100 without any solid moving part.
- a first end of heat transport path 150 may extend deep into shielding, including inner shielding 11 and even a cavity holding heat-generating stored objects, such as spent nuclear fuel 1.
- An opposite end of heat transport path 150 may pass to an outer portion, such as outer damper 160 or even to an exterior of cask 10, to be in direct communication with the environment.
- FIG. 2B is a detail of heat transport path 150 from FIG. 1 A, showing a directional change in path 150 to avoid a direct, linear path from inside example embodiment heat transfer cask 100 to the surrounding environment.
- path 150 may be fully shielding, differently shielding, or not necessarily shielding at all, a straight line from a radiation producing stored element, such as spent fuel 1, to outside cask 100 may provide an exposure path through which dangerous or unwanted radiation may escape.
- path 150 may change direction, such as via lateral jog in FIG. 2B through surrounding outer shielding 12, to remove any straight path through radiation shielding of cask 100.
- Flow path 150 may curve, angle, bend, etc. in any number of different directions to prevent any escape line from inside cask 100 to outside the same. Additionally or alternatively, flow path 150 may incorporate shielding materials or be shielded at ends to further prevent radiation escape.
- Heat transport path 150 readily transmits heat between its portions near an inside of cask 100 and outside cask 100.
- heat transport path 150 may be a solid, heat conductive rod such as copper, iron, tungsten, aluminum, and/or conductive alloys such as aluminum nitride or silicon carbide.
- heat transport path 150 may be a heat pipe with an internal transport path conducting heat via convection and conduction through an evaporating and condensing coolant. Any number of heat transport paths 150 may be used in example embodiments, necessary only to remove expected heat loads.
- sufficiently sized and numbered heat transport paths 150 such as 20 lkW heat pipes, may be used to ensure temperatures do not exceed or even approach 650 °C based on the radioactivity of objects placed into cask 100.
- Heat transport path 150 like other structural elements of cask 100, is fabricated of materials that are sufficiently strong to preserve the structural integrity of cask 100 while not undergoing substantial strength or material changes or degradation when exposed to radiation, including stainless steels, aluminum alloys, nickel alloys, zirconium alloys, carbides, etc. In this way, heat transport path 150 may readily allow heat to passively escape cask 100 while ensuring cask 100 is robust and maintains containment to radioactive elements inside, without external power or moving structures.
- Example embodiment heat transfer cask 100 may include dampers 160 at a cooling or ambient portion of heat transport path 150.
- dampers may form a skirt or ring about a perimeter of an end of cask 100, or be placed anywhere else about heat transfer path 150.
- Dampers 160 may be manually or automatically opened to allow air flow and convection over heat transfer path 150, maximizing heat transfer out of cask 100, or partially opened or closed to allow heating of cask 100.
- Example embodiment heat transfer cask 100 may include a convective jacket or ring 110 that acts as a conductive heat reservoir.
- ring 110 may be a 2-inch sodium ring that will melt and be convective liquid at typical inner temperatures of cask 100.
- Ring 110 may be in direct or nearby connection with a heated or innermost portion of heat transport path 150 to transfer heat to path 150, which is then transferred through path 150 to an outer portion, such as near dampers 160.
- Ring 110 may be between inner shielding 11 and outer shielding 12, which may be thinner than in related art casks to achieve a same outer diameter, or same or larger sizes with a different outer diameter.
- Inner cavity 160 defined by shielding and internal structural dividers of example embodiment cask 100 may be sized to house any number of heat-generating materials, including as such as six fuel assemblies 1 for liquid metal reactors, light or heavy water reactors, graphite-moderated reactors, etc. Inner cavity need not be filled with helium but can use any inert filler, including argon or nitrogen, given the heat transfer abilities of cask 100.
- Central rod 105 may be used to pack cavity 160, absorb radiation, and/or extend from a top of cask 100 to allow handling.
- central rod 105 may be strong boron carbide that is both a neutron absorber and is structural with the remainder of cask 100 and allows handling the same where it passes up through an end.
- cavity 160 may be surrounded by a perimeter of several heat transport paths 150 as well as shielding 11/12 and ring 110, in any ordering or thickness with structural separators. In this way, cavity 160 may be evenly and fully cooled/heated by transport paths 150 and ring 110.
- Example embodiment heat transfer cask 100 may include immersion heating rod 120 to heat ring 110 and contents of cavity 160 to a desired temperature.
- Immersion heating rods 120 may be similarly positioned to heat transport paths 150 and work in a largely opposite manner, delivering heat into, or generating heat in, cask 100.
- immersion heating rods 120 may be electric resistant heaters with power connections 121 near a top end of casks 100 to heat rods 120 and conduct the heat down into ring 110 and/or cavity 160.
- Rods 120 may be staggered about a perimeter into ring 110 with heat transport paths 120, as shown in FIG. 2C, for even heating and cooling.
- Example embodiment heat transfer cask 100 may include a lid or seam at an end allowing insertion or removal of contents of cavity 160 during this time, and cask 100 may be kept open and at an operating temperature during all loading and unloading because it is kept at an operating temperature by immersion heating rod 120.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
Description
Claims
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
EP20900437.3A EP4073824A4 (en) | 2019-12-11 | 2020-12-11 | Passive heat removal casks and methods of using the same |
CA3161203A CA3161203A1 (en) | 2019-12-11 | 2020-12-11 | Passive heat removal casks and methods of using the same |
JP2022535235A JP2023509325A (en) | 2019-12-11 | 2020-12-11 | Passive heat removal cask and method of use |
Applications Claiming Priority (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US201962946901P | 2019-12-11 | 2019-12-11 | |
US62/946,901 | 2019-12-11 | ||
US17/120,097 US11437159B2 (en) | 2019-12-11 | 2020-12-11 | Passive heat removal casks and methods of using the same |
US17/120,097 | 2020-12-11 |
Publications (2)
Publication Number | Publication Date |
---|---|
WO2021119557A2 true WO2021119557A2 (en) | 2021-06-17 |
WO2021119557A3 WO2021119557A3 (en) | 2021-08-19 |
Family
ID=76329105
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/US2020/064713 WO2021119557A2 (en) | 2019-12-11 | 2020-12-11 | Passive heat removal casks and methods of using the same |
Country Status (4)
Country | Link |
---|---|
US (1) | US11437159B2 (en) |
JP (1) | JP2023509325A (en) |
CA (1) | CA3161203A1 (en) |
WO (1) | WO2021119557A2 (en) |
Citations (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB867267A (en) | 1958-10-17 | 1961-05-03 | Edlow Lead Company | Improvements in or relating to shipping casks for transporting radioactive materials |
US3780306A (en) | 1971-05-27 | 1973-12-18 | Nat Lead Co | Radioactive shipping container with neutron and gamma absorbers |
DE2801946A1 (en) | 1978-01-18 | 1979-07-19 | Amtrust Ag | Radioactive components embedded in solidified slats mixt. in container - for storage or transport as compact easily remelted unit |
EP0403756A1 (en) | 1989-06-19 | 1990-12-27 | Westinghouse Electric Corporation | Reactor vessel annealing system |
US6802671B1 (en) | 1999-03-30 | 2004-10-12 | Commissariat A L'energie Atomique | Installation for very long term storage of heat-generating products such as nuclear waste |
JP2009168775A (en) | 2008-01-21 | 2009-07-30 | Tokyo Electric Power Co Inc:The | Heat recovery system of spent fuel |
US20140177775A1 (en) | 2012-12-26 | 2014-06-26 | Eric Paul LOEWEN | Cooling systems for spent nuclear fuel, casks including the cooling systems, and methods for cooling spent nuclear fuel |
US20150243385A1 (en) | 2012-08-14 | 2015-08-27 | Smr Inventec, Llc | Passively-cooled spent nuclear fuel pool system and method therefor |
JP5889287B2 (en) | 2010-06-02 | 2016-03-22 | テーエヌ・アンテルナシオナルTNInternational | Package for transporting and storing radioactive material having improved heat conduction means and container for transporting and storing radioactive material comprising the same |
KR101903130B1 (en) | 2017-01-02 | 2018-10-01 | 한국전력기술 주식회사 | Transport and storage container for spent nuclear fuel |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6805815B1 (en) * | 2000-05-24 | 2004-10-19 | Hanford Nuclear Service, Inc. | Composition for shielding radioactivity |
KR200228725Y1 (en) | 2000-12-27 | 2001-07-19 | 김선일 | Radiation tube for high tempreture |
KR101503266B1 (en) | 2013-07-18 | 2015-03-18 | 국립대학법인 울산과학기술대학교 산학협력단 | Decay Heat Removal System By Using Hybrid Heat Pipe Having Coolant And Neutron Absorber For Cooling A Nuclear Power Plant |
US11430579B2 (en) * | 2017-02-27 | 2022-08-30 | Charles W. Pennington | Apparatus and methods for storing hazardous waste materials by encasing same in a fusible metal alloy |
-
2020
- 2020-12-11 WO PCT/US2020/064713 patent/WO2021119557A2/en unknown
- 2020-12-11 JP JP2022535235A patent/JP2023509325A/en active Pending
- 2020-12-11 US US17/120,097 patent/US11437159B2/en active Active
- 2020-12-11 CA CA3161203A patent/CA3161203A1/en active Pending
Patent Citations (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB867267A (en) | 1958-10-17 | 1961-05-03 | Edlow Lead Company | Improvements in or relating to shipping casks for transporting radioactive materials |
US3780306A (en) | 1971-05-27 | 1973-12-18 | Nat Lead Co | Radioactive shipping container with neutron and gamma absorbers |
DE2801946A1 (en) | 1978-01-18 | 1979-07-19 | Amtrust Ag | Radioactive components embedded in solidified slats mixt. in container - for storage or transport as compact easily remelted unit |
EP0403756A1 (en) | 1989-06-19 | 1990-12-27 | Westinghouse Electric Corporation | Reactor vessel annealing system |
US6802671B1 (en) | 1999-03-30 | 2004-10-12 | Commissariat A L'energie Atomique | Installation for very long term storage of heat-generating products such as nuclear waste |
JP2009168775A (en) | 2008-01-21 | 2009-07-30 | Tokyo Electric Power Co Inc:The | Heat recovery system of spent fuel |
JP5889287B2 (en) | 2010-06-02 | 2016-03-22 | テーエヌ・アンテルナシオナルTNInternational | Package for transporting and storing radioactive material having improved heat conduction means and container for transporting and storing radioactive material comprising the same |
US20150243385A1 (en) | 2012-08-14 | 2015-08-27 | Smr Inventec, Llc | Passively-cooled spent nuclear fuel pool system and method therefor |
US20140177775A1 (en) | 2012-12-26 | 2014-06-26 | Eric Paul LOEWEN | Cooling systems for spent nuclear fuel, casks including the cooling systems, and methods for cooling spent nuclear fuel |
KR101903130B1 (en) | 2017-01-02 | 2018-10-01 | 한국전력기술 주식회사 | Transport and storage container for spent nuclear fuel |
Non-Patent Citations (1)
Title |
---|
See also references of EP4073824A4 |
Also Published As
Publication number | Publication date |
---|---|
US20210225542A1 (en) | 2021-07-22 |
WO2021119557A3 (en) | 2021-08-19 |
JP2023509325A (en) | 2023-03-08 |
CA3161203A1 (en) | 2021-06-17 |
US11437159B2 (en) | 2022-09-06 |
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