Evaluation of FSV-1 cask for the transport of LWR irradiated fuel assemblies

Technical Report · Thu May 01 00:00:00 EDT 1980

DOI:https://doi.org/10.2172/5250348· OSTI ID:5250348

The Model FSV-1 spent fuel shipping cask was designed by General Atomic Company (GA) to service the Fort St. Vrain (FSV) nuclear generating station, a High Temperature Gas Reactor (HTGR) owned and operated by Public Service Company of Colorado (PSC). This report presents an evaluation of the suitability of the FSV-1 cask for the transport of irradiated Light Water Reactor (LWR) fuel assemblies from both Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). The FSV-1 cask evaluation parameters covered a wide spectrum of LWR fuel assemblies, based on burnup in Megawatt Days/Metric Ton of Heavy Metal (MWD/MTHM) and years of decay since irradiation. The criteria for suitability included allowable radiation dose rates, cask surface and interior temperatures and the Gross Vehicle Weight (GVW) of the complete shipping system.

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: AT03-80SF10791
• OSTI ID: 5250348
• Report Number(s): GA-A-15828; TTC-0119; TRN: 80-013869
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
SPENT FUEL CASKS
TRANSPORT
BWR TYPE REACTORS
EVALUATION
PWR TYPE REACTORS
SPENT FUEL ELEMENTS
CASKS
CONTAINERS
FUEL ELEMENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
420204* - Engineering- Shipping Containers
050900 - Nuclear Fuels- Transport
Handling
& Storage