Criticality Safety and Shielding Design Issues in the Development of High-Capacity Cask for Truck Transport

Conference · Sun Apr 12 00:00:00 EDT 1992

OSTI ID:10166456

Boshoven, Jack K. ^[1]

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1. General Atomics, San Diego, CA (United States)

General Atomics (GA) will be submitting an application for certification to the US Nuclear Regulatory Commission (NRC) for the GA-4 and GA-9 Casks In 1992. The GA-4 and GA-9 Casks are high-capacity legal weight truck casks designed to transport light water reactor spent fuel assemblies. To maintain a capacity of four pressurized-water-reactor (PWR) spent fuel assemblies, the GA-4 Cask uses burnup credit as part of the criticality control for initial enrichments over 3.0 wt % U-235. Using the US Department of Energy (DOE) Burnup Credit Program as a basis, GA has performed burnup credit analysis which is included in the Safety Analysis Report for Packaging (SARP). The GA-9 Cask can meet the criticality safety requirements using the "fresh fuel'' assumption. Our approach to shielding design is to optimize the GA-4 and GA-9 Cask shielding configurations for minimum weights and maximum payloads. This optimization involves the use of the most effective shielding material, square cross-section geometry with rounded corners and tapered neutron shielding sections in the non-fuel regions.

• Research Organization: General Atomics, San Diego, CA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Civilian Radioactive Waste Management (RW)
• DOE Contract Number: AC07-88ID12698
• OSTI ID: 10166456
• Report Number(s): EGG-M-91455; CONF-920430-100; ON: DE92017853
• Resource Relation: Conference: 3. International High Level Radioactive Waste Management (IHLRWM) Conference, Las Vegas, NV (United States), 12-16 Apr 1992; Other Information: PBD: [1992]
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
SPENT FUELS
ROAD TRANSPORT
SPENT FUEL CASKS
DESIGN
SHIELDING
CRITICALITY
SAFETY
BURNUP
Nuclear Criticality Safety Program (NCSP)
Light Water Reactor (LWR)
Spent Fuel Assemblies
Pressurized-Water-Reactor (PWR)
Legal Weight Truck (LWT) Casks
Boiling-Water-Reactor (BWR)
Burnup Credit
Fresh Fuel
KENO
SCALE
420204
050900
SHIPPING CONTAINERS
TRANSPORT, HANDLING, AND STORAGE