Verification, Validation and Uncertainty Quantification of Multi-physics Modeling of Nuclear Reactors

Dr Avramova is a member of the US national validation canter (NEKVaC) and NEA/OECD Expert Group on Multi-Physics Validation (EGMPEBV), and the coordinator of the OECD/NEA LWR Uncertainty Analysis and Modelling (UAM) benchmark. In addition, she is coordinator and leader of three international NEA/OECD benchmark activities - the US NRC/OECD BFBT benchmark, NRC/OECD PSBT benchmark, and OECD/NEA benchmark on reactivity compensation with diluted boron by stepwise insertion of control rod cluster into the VVER-1000 core. She has more than 15 years' expertise and experience in verification, validation and uncertainty quantification of multi-physics modeling of nuclear reactors and has published more than 40 peer-reviewed papers in this area in journals and proceedings of international conferences. She is one of the developers and instructors of a residential and distance education graduate level course entitled "Verification, Validation and Uncertainty Quantification in Multi-Physics Nuclear Reactor Analysis" at PSU and NCSU, which is also taught internationally as a one-week short course. Dr Ivanov is a member of the US DOE national validation canter (NEKVaC) and the NEA/OECD Expert Group on Multi-Physics Validation (EGMPEBV), and coordinator of the IAEA Coordinated Research Program on HTGR Uncertainty Analysis in Modelling (UAM). In addition, he is coordinator and leader of six international NEA/OECD benchmark activities - US NRC/OECD PWR MSLB benchmark, US NRC/OECD BWR TT benchmark, DOE/CEA/OECD VVER CT benchmark, OECD/NEA VVER-1000 Kalinin-3 benchmark, OECD/NEA PBMR-400 benchmark, and NRC/OECD BWR Oskarshamn-2 Stability benchmark. He has more than 25 years' expertise and experience in verification, validation and uncertainty quantification of multi-physics modeling of nuclear reactors, with more than 60 peer-reviewed papers in this area in journals and proceedings of international conferences. He is one of the developers and instructors of a residential and distance education graduate level course entitled "Verification, Validation and Uncertainty Quantification in Multi-Physics Nuclear Reactor Analysis" at PSU and NCSU, which is also taught internationally as a one-week short course

1. Introduction
2. Transport phenomena in nuclear reactors
3. Neutron transport: cell and assembly calculations
4. Neutron transport: core calculations
5. One-/two-phase flow transport and heat transfer
6. Neutronic/thermal-hydraulic coupling
7. Conclusion