GA-4/GA-9 legal weight truck from reactor spent fuel shipping casks
The preliminary design report presents the results of General Atomics (GA) preliminary design effort to develop weight truck from reactor spent fuel shipping casks. The thermal evaluation of the Office of Civilian Radioactive Waste Management (OCRWM) cask considered normal and hypothetical accident conditions of transport. We employed analytical modeling as well as fire testing of the neutron shielding material to perform the evaluation. This document addresses the thermal design features of the cask, discusses thermal criteria, and summarizes the results of the thermal evaluation, as well as results of structural containment and nuclear evaluations that support the design. Also included are the results of trade-off studies. 69 refs., 103 figs., 76 tabs.
- Research Organization:
- General Atomics, San Diego, CA (USA)
- Sponsoring Organization:
- DOE/RW
- DOE Contract Number:
- AC07-88ID12698
- OSTI ID:
- 6782405
- Report Number(s):
- DOE/ID/12698-1-Vol.2; GA-A-19862-Vol.2; ON: DE90013719; TRN: 90-023046
- Country of Publication:
- United States
- Language:
- English
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GA-4 and GA-9 Legal Weight Truck Shipping Cask Development
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Related Subjects
CONTAINMENT
SPECIFICATIONS
SPENT FUEL CASKS
THERMAL ANALYSIS
SPENT FUELS
TRANSPORT
ACCIDENTS
COMPILED DATA
CRITICALITY
EQUIPMENT
FIRE RESISTANCE
MATHEMATICAL MODELS
OPERATION
PACKAGING
QUALITY ASSURANCE
SHIELDING
TESTING
THERMODYNAMIC PROPERTIES
TRANSPORT REGULATIONS
CASKS
CONTAINERS
DATA
ENERGY SOURCES
FUELS
INFORMATION
MATERIALS
NUCLEAR FUELS
NUMERICAL DATA
PHYSICAL PROPERTIES
REACTOR MATERIALS
REGULATIONS
420204* - Engineering- Shipping Containers