Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 148 / Number 2
Deokjung Lee, Thomas J. Downar, Anthony Ulses, Bedirhan Akdeniz, Kostadin N. Ivanov
Nuclear Science and Engineering
Volume 148 / Number 2 / October 2004 / Pages 291-305
Format:electronic copy (download)
An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the U.S. Nuclear Regulatory Commission coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. The objective of the analysis was to assess the performance of TRAC-M/PARCS on a BWR transient with significance in two-phase flow and spatial variations of the neutron flux. TRAC-M/PARCS results are found to be in good agreement with measured plant data for both steady-state and transient phases of the benchmark. Additional analyses of four fictitious extreme scenarios are performed to provide a basis for code-to-code comparisons and comprehensive testing of the thermal-hydraulics/neutronics coupling. The obtained results of sensitivity studies on the effect of direct moderator heating on transient simulation indicate the importance of this modeling aspect.
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