Investigation of Burnup Credit Allowance in the Criticality Safety Evaluation of Spent Fuel Casks

Conference · Sun Apr 08 00:00:00 EDT 1990

OSTI ID:7166814

Lake, W. H. ^[1]; Sanders, T. L. ^[2]; Parks, C. V. ^[3]

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1. US Department of Energy (USDOE), Washington DC (United States)
2. Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States). Transportation Systems Development Division
3. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

This presentation discusses work in progress on criticality analysis verification for designs which take account of the burnup and age of transported fuel. The work includes verification of cross section data, correlation with experiments, proper extension of the methods into regimes not covered by experiments, establishing adequate reactivity margins, and complete documentation of the project. Recommendations for safe operational procedures are included, as well as a discussion of the economic and safety benefits of such designs.

• Research Organization: US Department of Energy (USDOE), Washington, DC (United States); Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States). Transportation Systems Development Division; Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 7166814
• Report Number(s): CONF-900406-12; ON: DE90005447; TRN: 90-007968
• Resource Relation: Conference: 1. International Conference for High-Level Radioactive Waste Management, Las Vegas, NV (United States), 8-12 Apr 1990
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HIGH-LEVEL RADIOACTIVE WASTES
UNDERGROUND DISPOSAL
SPENT FUELS
BURNUP
CAPACITY
CERTIFICATION
COST ESTIMATION
CRITICALITY
DESIGN
EVALUATION
INVESTIGATIONS
MINIMIZATION
RECOMMENDATIONS
RISK ASSESSMENT
SAFETY
SPENT FUEL CASKS
TRANSPORT
VERIFICATION
ADMINISTRATIVE PROCEDURES
CASKS
CONTAINERS
ENERGY SOURCES
FUELS
MANAGEMENT
MATERIALS
NUCLEAR FUELS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR MATERIALS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
Nuclear Criticality Safety Program (NCSP)
Light Water Reactor (LWR)
Spent Fuel Shipping Casks
CAPSIZE Code
Legal Weight Truck (LWT) System
Pressurized Water Reactor (PWR)
Boiling Water Reactor (BWR)
Fuel Loading Errors
420204* - Engineering- Shipping Containers
052002 - Nuclear Fuels- Waste Disposal & Storage
054000 - Nuclear Fuels- Health & Safety