Abonnement à la biblothèque: Guest
Advanced Course in Heat Transfer in Nuclear Reactor Safety
September, 1-5, 1980, Dubrovnik, Yugoslavia

DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf


ISBN Print: 978-0-89116-223-0

1.3 Comparison of TRAC Calculations with Experimental Data

pages 87-110
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.40
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RÉSUMÉ

TRAC is an advanced best-estimate computer code for analyzing postulated accidents in light water reactors. This paper gives a brief description of the code followed by comparisons of TRAC calculations with data from a variety of separate-effects, system-effects, and integral experiments. Based on these comparisons, the capabilities and limitations of the early versions of TRAC are evaluated.

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