Comparison of the TRACG and MAPP-SBWR codes for SBWR safety analysis
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Methods for analyzing the transient behavior of containment systems during Design Basis Accident (DBA) and Severe Accident (SA) events are required for current and next generation nuclear power plants. As part of the certification process for the General Electric Simplified Boiling Water Reactor (SBWR), containment response to such conditions is being predicted by the TRACG and MAAP-SBWR codes respectively. The qualification process of MAAP-SBWR and TRACG includes simulating a reference DBA LOCA event and comparing the predicted SBWR responses. Results from the two independent calculations show that the codes predict similar plant responses in terms of pressures, temperatures, flow rates and other parameters. This result, combined with benchmarking against tests now in progress, confirms that the codes may be used to predict SBWR containment behavior with a high degree of confidence.
author list (cited authors)
Vierow, K. M., McDonald, D. B., Buchholz, C. E., & Fitch, J. R.