Maria Avramova

Associate Professor of Nuclear Engineering, Director of Reactor Dynamics and Fuel Modeling Group, Coordinator of CTF User’s Group

Dr. Avramova is currently an Associate Professor and Director of Reactor Dynamics and Fuel Modeling Group (RDFMG) at North Carolina State University. She earned her Ph.D. degree in nuclear engineering from Pennsylvania State University (PSU) in 2007. Prior to joining PSU in January 2001, she held a research scientist position at the Institute of Nuclear Research and Nuclear Energy, Bulgarian Academy of Science, Sofia, Bulgaria. After her graduation, Dr. Avramova has held positions at PSU of post-doctoral scholar, Assistant Professor, and Associate Professor of Nuclear Engineering.

Over the past years, she has led high visibility international projects such as the Organization for Economic Co-operation and Development, Nuclear Energy Agency (OECD-NEA) / United States Nuclear Regulatory Commission (U.S. NRC) BWR Full-size Fine-mesh Bundle Test (BFBT) benchmark and the OECD-NEA/U.S.NRC PWR Subchannel and Bundle Tests (PSBT) benchmark. She is also one of the coordinators of the OECD LWR Uncertainty Analysis in Modeling (UAM) Benchmark, which is on-going and will continue for next few years.

Dr. Avramova has taught undergraduate, graduate, and post-graduate courses in the areas of introduction to nuclear engineering, advanced reactor design, design principles of reactor systems, reactor core thermal-hydraulics and uncertainty quantification, reactor kinetics and dynamics, nuclear fuel performance, and high fidelity multi-physics nuclear reactor simulations. Dr. Avramova has advised and graduated 10 PhD students, 15 MS students, and 38 MEng students. Dr. Avramova has published more than 100 papers in peer-reviewed journals and proceedings of international conferences.


Ph.D. 2007

Nuclear Engineering

Pennsylvania State University

Research Description

Dr. Avramova's research areas include reactor thermal-hydraulics; core design; transient and safety analysis; multi-physics and multi-scale simulations; verification and validation; and uncertainty and sensitivity analysis.


COBRA-TF (CTF) calculation tool in Frame of TRACE-PARCS Program
Kernkraftwerk Leibstadt AG(9/01/16 - 8/31/17)
Research Activities in the field of development and coupling COBRA-TF code version for research and power reactors.
South African Nuclear Energy Corporation SOC Ltd (NESCA)(1/01/16 - 5/31/17)
Participation in the MPEBV efforts with the NEA
US Dept. of Energy (DOE)(2/10/16 - 9/30/17)
Development and Application of a Data-Driven Methodology for Validation of Risk Informed Safety Margin Characterization Models
US Dept. of Energy (DOE)(10/01/16 - 9/30/19)
Three-dimensional fuel pin model validation by prediction of hydrogen distribution in cladding and comparison with experiment
US Dept. of Energy (DOE)(12/01/15 - 2/04/17)
Accurate Modeling of Heterogeneous Radial Void Feedback on BWR Neutronics Calculations.
AREVA (1/01/16 - 12/31/18)
Faculty Development Program in Nuclear Engineering at North Carolina State University, 2014
US Nuclear Regulatory Commission(8/01/14 - 7/31/17)
Consortium For Advanced Simulations of LWRs - Oak Ridge National Laboratory (ORNL)
US Dept. of Energy (DOE)(11/23/11 - 9/30/19)