Pretest and posttest calculations of Semiscale Test S-07-10D with the TRAC computer program. [PWR]
The Transient Reactor Analysis Code (TRAC) developed at the Los Alamos National Laboratory was used to predict the behavior of the small-break experiment designated Semiscale S-07-10D. This test simulates a 10 per cent communicative cold-leg break with delayed Emergency Core Coolant injection and blowdown of the broken-loop steam generator secondary. Both pretest calculations that incorporated measured initial conditions and posttest calculations that incorporated measured initial conditions and measured transient boundary conditions were completed. The posttest calculated parameters were generally between those obtained from pretest calculations and those from the test data. The results are strongly dependent on depressurization rate and, hence, on break flow.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6463578
- Report Number(s):
- LA-UR-81-1556; CONF-810806-6; TRN: 81-012149
- Resource Relation:
- Conference: Conference on small break loss of coolant accident analysis in LWR's, Monterey, CA, USA, 25 Aug 1981
- Country of Publication:
- United States
- Language:
- English
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