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

Conference · Tue Sep 17 00:00:00 EDT 2002

OSTI ID:801710

Vinson, D W

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.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: AC09-96SR18500
• OSTI ID: 801710
• Report Number(s): WSRC-MS-2002-00729; TRN: US0203998
• Resource Relation: Conference: DOE SNF and Fissile Materials Management, Charleston, SC (US), 09/17/2002--09/20/2002; Other Information: PBD: 17 Sep 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
FISSILE MATERIALS
MANAGEMENT
NEUTRON ABSORBERS
NUCLEAR FUELS
WASTE FORMS
WASTES