The melt-dilute treatment of Al-base highly enriched DOE spent nuclear fuels: Principles and practices
The melt-dilute treatment technology program is focused on the development and implementation of a treatment technology for diluting highly enriched (>20% {sup 235}U) aluminum spent nuclear fuel to low enriched levels, <20% {sup 235}U and qualifying the LEU Al-SNF form for geologic repository storage. 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. The benefits accrued from this treatment process include the potential for significant volume reduction, reduced criticality potential, and the potential for enhanced SNF form characteristics. The emphasis within the development program to date has been on determining the process metallurgy and off-gas system design for the treatment of all types of Al SNF (UAl{sub x}, Al-U{sub 3}O{sub 8}, and Al-U{sub 3}Si{sub 2}). In determining the process metallurgy a wide range of alloys, representative of those expected in the Al-SNF form, have been fabricated and their product characteristics, namely microstructure, homogeneity, phase composition, and ternary constituent effects have been analyzed. As a result of the presence of species within the melt which will possess significant vapor pressures in the desired operating temperature range an off-gas system is necessary. Of the volatile species the one of greatest concern is {sup 137}Cs.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (US)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 20015796
- Resource Relation:
- Conference: 1998 Materials Research Society Fall Meeting, Boston, MA (US), 11/30/1998--12/04/1998; Other Information: Single article reprints are available from University Microfilms Inc., 300 North Zeeb Road, Ann Arbor, Michigan 48106; PBD: 1999; Related Information: In: Scientific basis for nuclear waste management XXII. Materials Research Society symposium proceedings: Volume 556, by Wronkiewicz, D.J.; Lee, J.H. [eds.], 1355 pages.
- Country of Publication:
- United States
- Language:
- English
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