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

[摘要] 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.

[发布日期] 2002-08-26 [发布机构] United States. Department of Energy. Yucca Mountain Project Office.

[关键词] Criticality;Waste Forms;Wastes;11 Nuclear Fuel Cycle And Fuel Materials;Nuclear Fuels