1982•Am. Soc. Mech. Eng., (Pap.); (United States)Requires access
TRAC-P1A assessment of a loss-of-coolant accident in the semiscale MOD-3 facility
J.J. Pyum
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Abstract
The TRAC (Transient Reactor Analysis Code) is being developed at the Los Alamos National Laboratory as an advanced ''bestestimate'' computer program for analysis of postulated hypothetical accidents in pressurized water reactors. As a part of the TRAC independent assessment efforts, a TRAC posttest analysis of Semiscale Mod-3 Test S-07-6 was conducted. The result of this analysis shows that the agreement between TRAC calculation and experimental data is not very good. In particular, TRAC does not predict the long term downcomer and core liquid level oscillations during the reflood phase.