Overview of INL RELAP5-3D system code and examples of application to reactor analysis.

ART-GCR Methods Lead
FRI, 02/10/2023 - 3:00PM TO 4:00PM
Spring 2023 Colloquium Series

RELAP5-3D is the latest in the RELAP5 code series developed at Idaho National Laboratory (INL) for the analysis of transients and accidents in water–cooled nuclear power plants and related systems as well as the analysis of advanced reactor designs. The RELAP5–3D code is an outgrowth of the one-dimensional RELAP5/MOD3 code developed at INL. The most prominent attribute that distinguishes RELAP5–3D from its predecessors is the fully integrated, multi-dimensional thermal-hydraulic and kinetic modeling capability. In this talk we will go through some of these features and how they are used to perform reactor transient analysis. Modelling approaches and results from some of the recent activities performed at INL will be presented.

About the Speaker:

Dr. Paolo BALESTRA obtained his Ph.D. in energy and environment with focus on nuclear engineering in the 2017 at the “La Sapienza” University of Rome. He is currently working at the Idaho National Laboratory (INL) as lead of the methods of the Advanced Reactor Technology - Gas Cooled Reactor (ART-GCR) DoE Program and managing the High Temperature Gas cooled Reactor multiphysics area of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. His current research efforts focus on development, Verification and Validation (V&V) of advanced Modelling and Simulation (M&S) tools for design and safety assessment of advanced reactor technology.