Material transport models for accident-induced flow in nuclear fuel cycle facilities

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

OSTI ID:5557183

Greenaugh, K C

Assessment of the environmental consequences of an accident in a fuel cycle facility ultimately involves calculating the atmospheric dispersion of radioactive materials and estimating the radiation dose to the surrounding population. Some uncertainty lies in the estimate of the nuclear facility source term to be used for atmospheric dispersion calculations. The developed models can be incorporated into a code that predicts the gas dynamics induced from fire, explosions, or tornado accidents to better estimate the source term at the atmospheric boundary of a nuclear fuel cycle facility.

• Research Organization: Nuclear Regulatory Commission, Washington, DC
• OSTI ID: 5557183
• 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

050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACCIDENTS
DISASTERS
DOSES
ENVIRONMENTAL TRANSPORT
EXPLOSIONS
FIRES
FUEL CYCLE CENTERS
HAZARDS
HEALTH HAZARDS
MASS TRANSFER
NUCLEAR FACILITIES
RADIATION DOSES
RADIATION HAZARDS
RADIOACTIVITY TRANSPORT
STORMS
TORNADOES
WIND