Radiation dose rates from consolidated fuel in current-generation shipping casks

Conference · Fri Nov 01 04:00:00 EST 1985 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5470474

Parks, C V; Hermann, O W; Knight, J R

As part of a US Department of Energy study of public risk from cask transport of consolidated and unconsolidated spent fuel cooled beyond 5 yr, radiation dose rates from two current-generation shipping casks were evaluated. The IF300 rail shipping cask, with a capacity of seven pressurized water reactor (PWR) assemblies, and NLI 1/2 truck shipping cask, with a capacity of one PWR assembly, were selected as appropriate cask models. A Westinghouse 17 x 17 fuel assembly with a 3.3 wt % /sup 235/U enrichment, operated at a specific power of 37.5 MW/MTU for 880 full-power days (20% downtime in history), and discharged at a burnup of 33 GWd/MTU was specified. Results for spent fuel cooling times of 5, 10, 15, and 25 yr are reported here. All calculations were performed using the SCALE computational system.

• Research Organization: Oak Ridge National Lab., TN
• OSTI ID: 5470474
• Report Number(s): CONF-851115-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 50
• Country of Publication: United States
• Language: English

Related Subjects

050900 -- Nuclear Fuels-- Transport
Handling
& Storage
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
ACTINIDES
BURNUP
CASKS
COMPUTER CODES
CONTAINERS
DOSES
ELEMENTS
ENRICHED URANIUM
FUEL ELEMENTS
HAZARDS
HEALTH HAZARDS
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
NATIONAL ORGANIZATIONS
PWR TYPE REACTORS
RADIATION DOSES
RADIATION HAZARDS
REACTOR COMPONENTS
REACTORS
S CODES
SELF-SHIELDING
SHIELDING
SLIGHTLY ENRICHED URANIUM
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
TRANSPORT
URANIUM
US DOE
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS