Simulating advanced reactor transients to support the NRC [Nuclear Regulatory Commission]

Work has been performed to determine a modeling methodology for an advanced evolutionary pressurized water reactor (PWR), specifically the Westinghouse AP-600. In the past, simulation of nuclear plant thermal-hydraulic performance with state-of-the-art computer codes like the US Nuclear Regulatory Commission's (NRC's) best-estimate code, TRAC has provided significant insights into plant performance. The NRC has taken on the task of reviewing and commenting on new design concepts with a strategy of reviewing conceptual designs, identifying major licensing issues, identifying design features needing verification, and issuing safety evaluation reports. TRAC-PF1/MOD2 and other state-of-the-art thermal-hydraulic simulation codes may be employed to support future NRC research in the area of advanced reactor transient analysis. Efforts at Los Alamos National Laboratory are focused on developing a preliminary TRAC input model for an advanced PWR to provide an understanding of advanced reactor concepts and issues of potential safety concern to the NRC