TRAC-PF1/MOD2 best-estimate analysis of a large-break LOCA in a 15 times 15 generic four-loop Westinghouse nuclear power plant [electronic resource].
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1992. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: (38 pages) : digital, PDF file
- Additional Creators:
- Los Alamos National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Calculations of a large-break loss-of-coolant accident (LOCA) in a 15 × 15 generic four-loop Westinghouse nuclear power plant with both the TRAC-PF1/MOD1 and TRAC-PF1/MOD2 computer codes will be presented. The Transient Reactor Analysis Code (TRAC) has been developed by Los Alamos National Laboratory to provide advanced best-estimate simulations of real postulated transients in pressurized light-water reactors (LWRs) and for many related thermal-hydraulic facilities. The latest released version of TRAC is TRAC-PF1/MOD2. Significant improvements and enhancements over the MOD1 version were implemented in the MOD2 heat-transfer and constitutive models. One of the most significant improvements in the MOD2 code has been the implementation of the two-step numerics method in the three-dimensional components, which can significantly reduce run times for long, slow transients. A very important area of improvement has been in the reflood heat-transfer models. Developmental assessment results (i.e., code comparisons with experimental data) will be discussed for several separate-effects and integral test, including analysis of the Upper Plenum Test Facility (UPTF), the Cylindrical Core Test Facility (CCTF), and the Loss-of-Fluid Test Facility (LOFT). The assessment results provide information on the anticipated accuracy for the best-estimate models in the MOD2 computer code. The MOD1 to MOD2 comparison will provide an estimate for the effect of improved heat-transfer models on predicted peak cladding temperatures.
- Published through SciTech Connect., 01/01/1992., "la-ur-92-203", " conf-920804--4", "DE92007435", American Society of Mechanical Engineers national heat transfer conference and exposition, San Diego, CA (United States), 9-12 Aug 1992., and Spore, J.W.; White, J.R.; Lin, J.C.; Cappiello, M.C.; Schnurr, N.M.
- Funding Information:
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