Open AccessRadionuclide methods validation with FSV [Fort St. Vrain] data
Author(s) -
V. Jovanović
Publication year - 1989
Language(s) - English
Resource type - Reports
DOI - 10.2172/453986
Subject(s) - fission , radionuclide , fission products , nuclear engineering , environmental science , graphite , nuclear fuel , radiochemistry , waste management , nuclear physics , engineering , chemistry , physics , neutron , organic chemistry
As part of the radionuclide methods verification program at GA, a fuel performance analysis of the Fort St. Vrain (FSV) core was performed using the reference fuel performance and fission gas release models. The purpose of the analysis was to predict the fuel and graphite temperature distributions, fuel particle failure, and fission gas release as a function of time, and to compare the predicted fission gas release with data taken as part of the FSV radiochemistry surveillance program. The analysis covered the entire operating time of the FSV plant except for the last 18 days prior to the final shutdown because the operating parameters and data for this period were not available when the analysis was performed. 3 refs., 29 figs., 5 tabs