Melt-Dilute Form of AI-Based Spent Nuclear Fuel Disposal Criticality Summary Report

Technical Report · Mon Aug 26 00:00:00 EDT 2002

DOI:https://doi.org/10.2172/802603· OSTI ID:802603

Vinson, D; Serika, A

Criticality analysis of the proposed melt-dilute (MD) form of aluminum-based spent nuclear fuel (SNF), under geologic repository conditions, was performed [1] following the methodology documented in the Disposal Criticality Analysis Methodology Topical Report [2]. 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.

• Research Organization: Yucca Mountain Project, Las Vegas, NV (United States)
• Sponsoring Organization: US Department of Energy (US)
• OSTI ID: 802603
• Resource Relation: Other Information: PBD: 26 Aug 2002
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CRITICALITY
NEUTRON ABSORBERS
NUCLEAR FUELS
WASTE FORMS
WASTES