Fission Product Volatilization and Off-Gas System Development in the Melt-Dilute Treatment Technology Program for Al-Based DOE Spent Nuclear Fuel
The melt-dilute treatment technology program is focused on the development and implementation of a treatment technology for diluting highly enriched (approximately 20 percent 235U) aluminum spent nuclear fuel to low enriched levels (less than 20 percent) 235U and qualifying the LEU Al-SNF form for geologic repository storage. Typically, many domestic and foreign research reactor fuel assemblies were manufactured using highly enriched uranium-aluminum alloys. These assemblies have been irradiated and the burn-up levels range from 30-70 percent. In order to reduce the enrichment of these assemblies prior to ultimate geologic repository disposal, the melt-dilute technology proposes to melt these SNF assemblies and then dilute with additions of depleted uranium. Dilution levels of less than 20 percent are desired. Benefits accrued from this process when compared to the direct disposal option include the potential for significant volume reduction, reduced criticality potential, and the potential for enhanced SNF form characteristics.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 14747
- Report Number(s):
- WSRC-MS-99-00831; TRN: US0106236
- Resource Relation:
- Conference: DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, CA (US), 06/04/2000--06/08/2000; Other Information: PBD: 5 Nov 1999
- Country of Publication:
- United States
- Language:
- English
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