Volatilization of Fission Products from Metallic Melts in the Melt-Dilute Treatment Technology Development for Al-Based DOE Spent Nuclear Fuels
The melt-dilute treatment technology is being developed to facilitate the ultimate disposition of highly enriched Al-Base DOE spent nuclear fuels in a geologic repository such as that proposed for Yucca Mountain. Currently, approximately 28 MTHM is expected to be returned to the Savannah River Site from domestic and foreign research reactors. The melt-dilute treatment technology will melt the fuel assemblies to reduce their volume and alloys them with depleted uranium to isotopically dilute the 235U concentration. The resulting alloy is cast into a form for long term geologic repository storage. Benefits accrued from the melt-dilute process include the potential for significant volume reduction; reduced criticality potential, and proliferation concerns. A critical technology element in the development of the melt-dilute process is the development of offgas system requirements. The volatilization of radioactive species during the melting stage of the process primarily constitutes the offgas in this process. Several of the species present following irradiation of a fuel assembly have been shown to be volatile or semi-volatile under reactor core melt-down conditions. Some of the key species that have previously been studied are krypton, iodine, and cesium. All of these species have been shown to volatilize during melting experiments however, the degree to which they are released is highly dependent upon atmosphere, fuel burnup, temperature, and fuel composition. With this in mind an analytical and experimental program has been undertaken to assess the volatility and capture of species under the melt-dilute operating conditions.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 14899
- Report Number(s):
- WSRC-MS-99-00847P; TRN: US0106843
- Resource Relation:
- Conference: MRS Fall Meeting, Boston, MA (US), 10/28/1999--11/03/1999; Other Information: PBD: 18 Nov 1999
- Country of Publication:
- United States
- Language:
- English
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Fission Product Volatilization and Off-Gas System Development in the Melt-Dilute Treatment Technology Program for Al-Based DOE Spent Nuclear Fuel
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Related Subjects
ALUMINIUM ALLOYS
DEPLETED URANIUM
EVAPORATION
FISSION PRODUCTS
FUEL ASSEMBLIES
SPENT FUELS
MELTING
DILUTION
HIGHLY ENRICHED URANIUM
WASTE FORMS
RADIOACTIVE WASTE DISPOSAL
OFF-GAS SYSTEMS
VOLATILE MATTER
RADIOACTIVE WASTE PROCESSING