Radioactive source term models in a compartment fire code
Models for the release of airborne radioactivity in fires have been developed. These radioactive source term models are used as subroutines in a compartment fire code called FIRIN. Each model is based on release factors developed using information from experiments. Models are developed for the following release mechanisms: burning of contaminated combustible solids; burning of contaminated combustible liquids; heating of noncombustible contaminated surfaces; heating of unpressurized radioactive liquids; pressurized releases of radioactive powders; and pressurized releases of radioactive liquids. The potential for release from these mechanisms was examined in an analysis of three types of fuel cycle facility fires. The types of fires considered were mixed oxide ( MOX) general facility fires, MOX stored combustible waste fires, and solvent extraction fires in fuel reprocessing plants. Input parameters were varied to determine relative importance of release mechanisms and sensitivity of predicted releases to changes in initial conditions. Total radioactive material released ranged from 8 X 10/sup -4/ g of plutonium (0.002% of material at risk) given off in a combustible waste fire to 75 g of mixed isotopes (0.3% of material at risk) given off in a solvent extraction fire. Fuel loading and burn area were the parameters that caused the greatest change in total release of radioactive material. Changes in ventilation rate also made a significant difference in release for overventilated fires, but not for underventilated fires. Work is under way at Battelle Pacific Northwest Laboratory to improve the models for burning of contaminated combustible solids and liquids.
- Research Organization:
- Pacific Northwest Laboratory, Richland, Washington
- OSTI ID:
- 6353296
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 69:1; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220900* -- Nuclear Reactor Technology-- Reactor Safety
BATTELLE PACIFIC NORTHWEST LABORATORIES
COMPARTMENTS
COMPUTER CODES
COMPUTERIZED SIMULATION
ENVIRONMENTAL TRANSPORT
F CODES
FIRE HAZARDS
FIRES
FISSION PRODUCT RELEASE
FUEL CYCLE
FUEL REPROCESSING PLANTS
FUELS
HAZARDS
HEALTH HAZARDS
MASS TRANSFER
MIXED OXIDE FUELS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
RADIATION HAZARDS
RADIONUCLIDE MIGRATION
REACTOR FUELING
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
SOLID FUELS
SPENT FUEL STORAGE
STORAGE
THERMAL POWER PLANTS
US DOE
US ERDA
US ORGANIZATIONS