Melt-Dilute Form of AI-Based Spent Nuclear Fuel Disposal Criticality Summary Report [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 2002.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 1 pages : digital, PDF file
- Additional Creators:
- United States. Department of Energy. Yucca Mountain Project Office, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Criticality analysis of the proposed melt-dilute (MD) form of aluminum-based spent nuclear fuel (SNF), under geologic repository conditions, was performed  following the methodology documented in the Disposal Criticality Analysis Methodology Topical Report . This methodology evaluates the potential for nuclear criticality for a waste form in a waste package. Criticality calculations show that even with waste package failure, followed by degradation of material within the waste package and potential loss of neutron absorber materials, sub-critical conditions can be readily demonstrated for the MD form of aluminum-based SNF.
- Report Numbers:
- E 1.99:802603
- Published through SciTech Connect.
D. Vinson; A. Serika.
View MARC record | catkey: 14410436