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Title: TRAC (Transient Reactor Analysis Code) analyses of Savannah River 1985 L-Area test series

Conference ·
OSTI ID:6756869

Thermal-hydraulic benchmark analyses have been performed using the Transient Reactor Analysis Code (TRAC) for the Savannah River 1985 L-Area AC process flow tests. TRAC models were prepared and run for each of the 11 L-Area steady-state tests. Comparison of the TRAC results with the Savannah River data focused on coolant pressures and flows in the six external loops as well as the magnitude and distribution of coolant pressures in the upper plenum. In general, the TRAC pressures, pressure drops, and coolant flow rates in the external loops are in reasonable agreement with the data. Moreover, although the TRAC results tend to slightly overpredict the upper- plenum pressure data, the results do provide an excellent representation of the radial and azimuthal variations in upper-plenum pressures. Thus, the 1985 L-Area benchmarks lend credibility and confidence to both TRAC and the TRAC Savannah River plant model. 4 refs., 10 figs., 4 tabs.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
DOE/DP
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
6756869
Report Number(s):
LA-UR-90-1963; CONF-900608-44; ON: DE90013179
Resource Relation:
Conference: American Nuclear Society annual meeting, Nashville, TN (USA), 10-14 Jun 1990
Country of Publication:
United States
Language:
English