Summary Report of Laboratory Critical Experiment Analyses Performed for the Disposal Criticality Analysis Methodology

Technical Report · Thu Sep 09 00:00:00 EDT 1999

DOI:https://doi.org/10.2172/839541· OSTI ID:839541

Scaglione, J. M. ^[1]

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1. Yucca Mountain Project, Las Vegas, NV (United States)

This report, "Summary Report of Laboratory Critical Experiment Analyses Performed for the Disposal Criticality Analysis Methodology”, contains a summary of the laboratory critical experiment (LCE) analyses used to support the validation of the disposal criticality analysis methodology. The United States Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is developing a methodology for criticality analysis to support disposal of commercial spent nuclear fuel in a geologic repository. A supplement to the Disposal Criticality Analysis Methodology Topical Report is scheduled to be submitted to the United States Nuclear Regulatory Commission (NRC) for formal review later in 1999. This technical report is one of a series of reports that provides a summary of the results of the analyses that support the development of the disposal criticality analysis methodology. The objective of this report is to present a summary of the LCE analyses' results. These results demonstrate the ability of MCNP to accurately predict the critical multiplication factor (k_eff) for fuel with different configurations. Results from the LCE evaluations will support the development and validation of the criticality models used in the disposal criticality analysis methodology. These models and their validation have been discussed in the “Disposal Criticality Analysis Methodology Topical Report” (CRWMS M&O 1998a)

• Research Organization: Yucca Mountain Project, Las Vegas, NV (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC08-91RW00134
• OSTI ID: 839541
• Report Number(s): B00000000-01717-5705-00076-REV-02; MOL.19990920.0167, DC 22935; TRN: US0502654
• Resource Relation: Other Information: PBD: 9 Sep 1999
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
42 ENGINEERING
CRITICALITY
MULTIPLICATION FACTORS
VALIDATION
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE DISPOSAL
YUCCA MOUNTAIN
SAFETY ANALYSIS
Nuclear Criticality Safety Program (NCSP)
Criticality
Validation
Radioactive Waste
Waste Disposal
Safety