Radionuclide methods validation with FSV [Fort St. Vrain] data [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1989.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 54 pages : digital, PDF file
- Additional Creators:
- General Atomic Company
United States. Department of Energy
United States. Department of Energy. Office of Scientific and Technical Information
- 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.
- Published through SciTech Connect.
- Funding Information:
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