MX2023012200A - Zamak stabilization of spent sodium-cooled reactor fuel assemblies. - Google Patents
Zamak stabilization of spent sodium-cooled reactor fuel assemblies.Info
- Publication number
- MX2023012200A MX2023012200A MX2023012200A MX2023012200A MX2023012200A MX 2023012200 A MX2023012200 A MX 2023012200A MX 2023012200 A MX2023012200 A MX 2023012200A MX 2023012200 A MX2023012200 A MX 2023012200A MX 2023012200 A MX2023012200 A MX 2023012200A
- Authority
- MX
- Mexico
- Prior art keywords
- zamak
- sodium
- fuel assemblies
- sheath
- spent fuel
- Prior art date
Links
- 229910000842 Zamak Inorganic materials 0.000 title abstract 8
- 230000000712 assembly Effects 0.000 title abstract 5
- 238000000429 assembly Methods 0.000 title abstract 5
- 239000003758 nuclear fuel Substances 0.000 title 1
- 230000006641 stabilisation Effects 0.000 title 1
- 238000011105 stabilization Methods 0.000 title 1
- 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 abstract 4
- 229910052708 sodium Inorganic materials 0.000 abstract 4
- 239000011734 sodium Substances 0.000 abstract 4
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 3
- 239000000446 fuel Substances 0.000 abstract 2
- 239000007788 liquid Substances 0.000 abstract 2
- 238000000034 method Methods 0.000 abstract 2
- 229910045601 alloy Inorganic materials 0.000 abstract 1
- 239000000956 alloy Substances 0.000 abstract 1
- 239000002826 coolant Substances 0.000 abstract 1
- 238000001816 cooling Methods 0.000 abstract 1
- 230000001681 protective effect Effects 0.000 abstract 1
- 239000007787 solid Substances 0.000 abstract 1
- 230000000087 stabilizing effect Effects 0.000 abstract 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
- 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
- G21C19/32—Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
-
- 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
- G21F5/008—Containers for fuel elements
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Methods and systems for stabilizing spent fuel assemblies from sodium-cooled nuclear reactors using Zamak are described herein. It has been determined that there is a synergism between Zamak and sodium that allows Zamak to form thermally-conductive interface with the sodium-wetted surfaces of the fuel assemblies. In the method, one or more spent fuel assemblies are removed from the sodium coolant pool and placed in a protective sheath. The remaining volume of the sheath is then filled with liquid Zamak. To a certain extent Zamak will dissolve and alloy with sodium remaining on the fuel assemblies. Excess sodium that remains undissolved is displaced from the sheath by the Zamak fill. The Zamak is then cooled until solid and the sheath sealed. The resulting Zamak-stabilized spent fuel assembly is calculated to have sufficient internal thermal conductivity to allow it to be stored and transported without the need for liquid cooling.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| PCT/US2021/027249 WO2022220819A1 (en) | 2021-04-14 | 2021-04-14 | Zamak stabilization of spent sodium-cooled reactor fuel assemblies |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| MX2023012200A true MX2023012200A (en) | 2023-12-06 |
Family
ID=76325587
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| MX2023012200A MX2023012200A (en) | 2021-04-14 | 2021-04-14 | Zamak stabilization of spent sodium-cooled reactor fuel assemblies. |
Country Status (6)
| Country | Link |
|---|---|
| EP (1) | EP4324003A1 (en) |
| JP (1) | JP2024514626A (en) |
| KR (1) | KR20230172530A (en) |
| CA (1) | CA3212732A1 (en) |
| MX (1) | MX2023012200A (en) |
| WO (1) | WO2022220819A1 (en) |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2911185A1 (en) * | 1979-03-22 | 1980-10-02 | Amtrust Ag | Spent nuclear fuel element storage basin - with stainless steel granules filling voids between fuel rods |
| US10878972B2 (en) * | 2019-02-21 | 2020-12-29 | Deep Isolation, Inc. | Hazardous material repository systems and methods |
-
2021
- 2021-04-14 MX MX2023012200A patent/MX2023012200A/en unknown
- 2021-04-14 JP JP2023562941A patent/JP2024514626A/en active Pending
- 2021-04-14 KR KR1020237039104A patent/KR20230172530A/en active Search and Examination
- 2021-04-14 WO PCT/US2021/027249 patent/WO2022220819A1/en active Application Filing
- 2021-04-14 CA CA3212732A patent/CA3212732A1/en active Pending
- 2021-04-14 EP EP21731002.8A patent/EP4324003A1/en active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| WO2022220819A1 (en) | 2022-10-20 |
| JP2024514626A (en) | 2024-04-02 |
| EP4324003A1 (en) | 2024-02-21 |
| KR20230172530A (en) | 2023-12-22 |
| CA3212732A1 (en) | 2022-10-20 |
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