TMI MSLB analysis using TRAC-PF1 coupled with three-dimensional kinetics

The Main Steam Line Break (MSLB) accident in a pressurized water reactor is characterized by significant space-time effects in the core caused by asymmetric cooling and assumed stuck-out rod during reactor trip. Simulation of transients involving asymmetric core power peaking requires evaluation of the core response from a multi-dimensional perspective. These effects are analyzed in this paper for TMI Cycle 10 using the TRAC-PF1/NEM computer code. The TRAC-PF1/NEM methodology utilizes a closely coupled transient three-dimensional thermal-hydraulics vessel and three-dimensional neutronics core models supplemented by 1D simulation of the remainder of the reactor coolant system. A comparison of the 3-D kinetics results to a compatible point kinetics prediction is also performed