Spent and Fresh Fuel Shipping Cask Considerations

Conference · Sun Nov 16 04:00:00 EST 1975 · Proceedings of the Conference on Remote Systems Technology

OSTI ID:4003965

Shappert, L. B. ^[1]; Unger, W. E. ^[1]; Freedman, J. M. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

A program to provide basic information for cask design and safety has been conducted for over ten years at Oak Ridge National Laboratory. Principal problem areas in liquid-metal fast breeder reactor (LMFBR) spent-fuel shipping casks are identified as heat transfer, structures and containment, criticality and shielding. Solutions in the problem areas, as well as the need for future work, are addressed by describing an LMFBR conceptual design cask. A new program, which is under way at Sandia Laboratories, Albuquerque, New Mexico, is aimed at producing technology useful to industry and government. Technologies are being developed in areas of hazards analysis, heat transfer, shielding, structures and containment, and spent-fuel characterization, substantiated by hot laboratory verification. Particular emphasis will be placed on establishing qualification tests based on accident experience. Handling requirements and limitations are noted throughout the paper.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• NSA Number: NSA-33-032325
• OSTI ID: 4003965
• Conference Information: Journal Name: Proceedings of the Conference on Remote Systems Technology Journal Volume: 23
• 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
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
Cask Design
Containment Problems
Criticality Problems
FUEL ELEMENTS
Future Work
Handling Requirements
Heat Transfer Problems
Limitations
Liquid-Metal Fast Breeder Reactor (LMFBR)
Nuclear Criticality Safety Program (NCSP)
Program Development
RESEARCH PROGRAMS
SPENT FUEL ELEMENTS
Safety
Shielding Problems
Solutions
Spent-Fuel Shipping Casks
Structures Problems
TRANSPORT