Melt-Dilute Form of Al-Based Spent Nuclear Fuel Disposal Criticality Summary Report
Conference
·
OSTI ID:801710
- Savannah River Site (SRS), Aiken, SC (United States)
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:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 801710
- Report Number(s):
- WSRC-MS--2002-00729
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
42 ENGINEERING
Aluminum-Based Spent Nuclear Fuel (SNF)
CRITICALITY
FISSILE MATERIALS
MANAGEMENT
Melt-Dilute (MD)
NEUTRON ABSORBERS
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
WASTE FORMS
WASTES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
42 ENGINEERING
Aluminum-Based Spent Nuclear Fuel (SNF)
CRITICALITY
FISSILE MATERIALS
MANAGEMENT
Melt-Dilute (MD)
NEUTRON ABSORBERS
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
WASTE FORMS
WASTES