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Buxton, L.D.; Kmetyk, L.N.; Dobranich, D.; Byers, R.K.; Peterson, A.C.; Elrick, M.G.
Sandia National Labs., Albuquerque, NM (USA)1984
Sandia National Labs., Albuquerque, NM (USA)1984
AbstractAbstract
[en] Most of the results obtained so far in the assessment effort have been in good overall agreement with the available data. We have found no gross errors in predicted behavior which would indicate that the physical models or correlations contained in TRAC-PF1/MOD1 were totally inadequate for the range of parameters of interest in full-scale PWR analyses. The most serious deficiency noted could well be the apparent inability of the code to predict early-time quench behavior during large-break LOCAs. Many of the coding, documentation and modelling inadequacies identified in the course of our assessment calculations are being or have already been addressed by the code developers
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1984; 12 p; 12. water reactor safety research information meeting; Gaithersburg, MD (USA); 23-26 Oct 1984; CONF-8410142--20; Available from NTIS, PC A02/MF A01 as DE85000412
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