FASTGRASS: A mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions

Technical Report · Tue Sep 01 00:00:00 EDT 1992

DOI:https://doi.org/10.2172/7255051· OSTI ID:7255051

Rest, J; Zawadzki, S A ^[1]

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1. Argonne National Lab., IL (United States)

The primary physical/chemical models that form the basis of the FASTGRASS mechanistic computer model for calculating fission-product release from nuclear fuel are described. Calculated results are compared with test data and the major mechanisms affecting the transport of fission products during steady-state and accident conditions are identified.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7255051
• Report Number(s): NUREG/CR-5840; ANL-92/3; ON: TI92040783
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
FISSION PRODUCT RELEASE
F CODES
NUCLEAR FUELS
BARIUM
BUBBLES
CESIUM
GASES
GRAIN BOUNDARIES
IODINE
RADIATION EFFECTS
REACTOR ACCIDENTS
STRONTIUM
TELLURIUM
URANIUM DIOXIDE
XENON
ACCIDENTS
ACTINIDE COMPOUNDS
ALKALI METALS
ALKALINE EARTH METALS
CHALCOGENIDES
COMPUTER CODES
CRYSTAL STRUCTURE
ELEMENTS
ENERGY SOURCES
FLUIDS
FUELS
HALOGENS
MATERIALS
METALS
MICROSTRUCTURE
NONMETALS
OXIDES
OXYGEN COMPOUNDS
RARE GASES
REACTOR MATERIALS
SEMIMETALS
URANIUM COMPOUNDS
URANIUM OXIDES
220900* - Nuclear Reactor Technology- Reactor Safety
220504 - Nuclear Reactor Technology- Environmental Aspects- Design Basis & Hypothetical Accidents- (1992-)
990200 - Mathematics & Computers