VICTORIA: A mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions. Revision 1
Author(s) -
T Heams,
D. C. Williams,
Nicole E. Johns,
Anne B. Mason,
Nathan E. Bixler,
A. J. Grimley,
Christopher J. Wheatley,
Lawrence W. Dickson,
I Osborn-Lee,
P. Domagala,
S.A. Zawadzki,
J. Rest,
C. M. O'd. Alexander,
R Lee
Publication year - 1992
Language(s) - English
Resource type - Reports
DOI - 10.2172/10121041
Subject(s) - nuclear fission product , coolant , fission products , radionuclide , nuclear engineering , light water reactor , environmental science , fission , nuclear reactor , fuel element failure , loss of coolant accident , nuclear physics , engineering , physics , neutron
The VICTORIA model of radionuclide behavior in the reactor coolant system (RCS) of a light water reactor during a severe accident is described. It has been developed by the USNRC to define the radionuclide phenomena and processes that must be considered in systems-level models used for integrated analyses of severe accident source terms. The VICTORIA code, based upon this model, predicts fission product release from the fuel, chemical reactions involving fission products, vapor and aerosol behavior, and fission product decay heating. Also included is a detailed description of how the model is implemented in VICTORIA, the numerical algorithms used, and the correlations and thermochemical data necessary for determining a solution. A description of the code structure, input and output, and a sample problem are provided.
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