Development of the FACE computer code to evaluate the safety of an air ventilation system of an air ventilation system during a postulated solvent fire in a nuclear fuel reprocessing plant

Journal Article · Sat May 01 00:00:00 EDT 1993 · Nuclear Technology; (United States)

OSTI ID:6549615

Nishio, Gunji ^[1]; Yamazaki, Noboru ^[2]

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1. Japan Atomic Energy Research Inst., Ibaraki (Japan)
2. Fuji Research Inst., Tokyo (Japan)

The FACE computer code was developed to calculate postulated solvent fire behavior in the extraction process of a nuclear fuel reprocessing plant. The FACE code calculates temperature, pressure, and off-gas flow rate by one- and two-dimensional thermofluid analyses. The code uses this information to evaluate the safety of the associated air ventilation system as demonstrated by its ability to confine the fire-generated radioactive particles by transport, deposition, and filtration of smoke. The mathematical models in FACE were verified by comparison of FACE calculations with the results of Japan Atomic Energy Research Institute fire demonstration tests simulating a hypothetical solvent fire accident in the extraction process.

• OSTI ID: 6549615
• Journal Information: Nuclear Technology; (United States), Vol. 102:2; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
FUEL REPROCESSING PLANTS
VENTILATION SYSTEMS
SAFETY ANALYSIS
ACCIDENTS
EVALUATION
F CODES
FIRES
MATHEMATICAL MODELS
PARTICLES
RADIOACTIVE AEROSOLS
SAFETY
SMOKES
SOLVENTS
AEROSOLS
COLLOIDS
COMPUTER CODES
DISPERSIONS
NUCLEAR FACILITIES
RESIDUES
SOLS
050800* - Nuclear Fuels- Spent Fuels Reprocessing
054000 - Nuclear Fuels- Health & Safety