Zamak stabilization of spent sodium-cooled reactor fuel assemblies
US11837374B2 · kind B2 · utility
Assignee
Inventors
Key dates
| Filing date | Apr 14, 2021 |
| Grant date | Dec 5, 2023 |
| Priority date | — |
| Expiry date | Jan 5, 2042 |
Classification
- Technology area (CPC G)Physics
- CPC primaryG21F9/20
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
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.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.