Spent and fresh fuel shipping cask considerations
Conference
·
OSTI ID:4150933
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) 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 underway 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 discussed. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA); Sandia Labs., Albuquerque, N.Mex. (USA)
- NSA Number:
- NSA-33-003689
- OSTI ID:
- 4150933
- Report Number(s):
- SAND--75-5658; CONF-751101--24
- Country of Publication:
- United States
- Language:
- English
Similar Records
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·
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·
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·
OSTI ID:4130336
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·
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Related Subjects
*CASKS-- SAFETY
*FUEL ELEMENTS-- TRANSPORT
*LMFBR TYPE REACTORS-- FUEL ELEMENTS
420204* --Engineering--Facilities & Equipment--Shipping Containers
ACCIDENTS
CRITICALITY
DAMAGE
FAILURES
HAZARDS
HEAT TRANSFER
N52400* --Nuclear Materials & Waste Management-- Transportation
SHIELDING
SPENT FUELS
*FUEL ELEMENTS-- TRANSPORT
*LMFBR TYPE REACTORS-- FUEL ELEMENTS
420204* --Engineering--Facilities & Equipment--Shipping Containers
ACCIDENTS
CRITICALITY
DAMAGE
FAILURES
HAZARDS
HEAT TRANSFER
N52400* --Nuclear Materials & Waste Management-- Transportation
SHIELDING
SPENT FUELS