Preliminary best estimate analysis of whole core LOCA behavior. [PWR] [electronic resource].
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1978.
- Physical Description:
- Pages: 7 : digital, PDF file
- Additional Creators:
- United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Analyses of fuel behavior during LOCA have generally been performed for a single fuel rod (the ''hot rod'') of a reactor core. This type of analysis, even using best estimate assumptions, does not apply to the behavior of majority of the fuel rods in the core. Furthermore, burnup effects are normally considered only so far as the fill gas pressure and, partly, the stored energy are concerned. However, the gap closure and additional burnup effects strongly influence the fuel behavior during a transient. Consequently, the power history should be simulated for the fuel rod during its life prior to the accident analysis. The paper describes a preliminary best estimate analysis using the FRAP-S and FRAP-T codes, to determine the behavior of the fuel rods in an operating commercial 15 x 15 PWR core during a postulated loss of coolant accident (LOCA). The blowdown, refill, and reflood phases of the core were considered.
- Published through SciTech Connect., 01/01/1978., "conf-781105-68", ANS meeting, Washington, DC, USA, 12 Nov 1978., Charyulu, M.K., and Idaho National Engineering Lab., Idaho Falls (USA)
- Funding Information:
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