Full risk-informed resolution of the GSI-191: Simulations of loca scenarios using RELAP5-3D and MELCOR Conference Paper uri icon

abstract

  • 2017 by American Nuclear Society. All rights reserved. Different approaches have been provided by the US Nuclear Regulatory Commission for addressing the concerns raised by the GSI-191. The approaches proposed by the STPNOC pilot plant adopted deterministic thermal-hydraulic calculations supported by system codes to simulate the plant response under numerous configurations and plant conditions. The results obtained supported the Probabilistic Risk Assessment analysis, and helped the resolution of the GSI-191, proving the importance of selecting and using specialized system codes and modeling technique to perform realistic simulations of the reactor system in support of both deterministic and risk-informed methods.

published proceedings

  • International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017

author list (cited authors)

  • Vaghetto, R., Kee, E., Crook, T., & Hassan, Y.

complete list of authors

  • Vaghetto, R||Kee, E||Crook, T||Hassan, Y

publication date

  • January 2017