TRAC-PF1 developmental assessment

The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory to provide advanced best-estimate predictions of postulated accidents in light-water reactors. The TRAC-PF1 program provides this capability for pressurized water reactors and for many thermal-hydraulic experimental facilities. This report presents the results of initial developmental assessment calculations performed with TRAC-PF1 before its public release. All calculations were performed with the same code version. The assessment set consisted of 10 calculations, 9 of which predicted integral effects in the Semiscale, Loss-of-Fluid Test Facility, and Primarkreislaufe facilities, while the remaining calculation predicted a single-effect test conducted in the Dartmouth air-water countercurrent flow apparatus. Computer run times required to predict each integral test are reported and compared with earlier TRAC versions where possible