A5031592750- Nuclear reactor physics and engineering
- Nuclear Engineering Thermal-Hydraulics
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Heat transfer and supercritical fluids
- Graphite, nuclear technology, radiation studies
- Nuclear Physics and Applications
- Probabilistic and Robust Engineering Design
- Risk and Safety Analysis
- Fault Detection and Control Systems
- Fusion materials and technologies
- Heat Transfer and Boiling Studies
- Fluid Dynamics and Mixing
- Advanced Numerical Methods in Computational Mathematics
- Magnetic confinement fusion research
- Computational Fluid Dynamics and Aerodynamics
- Non-Destructive Testing Techniques
- Engineering Applied Research
- Laser-Plasma Interactions and Diagnostics
- Metallurgical Processes and Thermodynamics
- Catalytic Processes in Materials Science
- Digital Transformation in Industry
- Ophthalmology and Visual Health Research
- Advanced Power Generation Technologies
- Diverse Education and Engineering Focus
North Carolina State University
2016-2024
Sciences pour L’Œnologie
2024
Institut d'Etudes Politiques de Paris
2024
Idaho National Laboratory
2020
North Central State College
2019
Core Laboratories (United States)
2019
Pennsylvania State University
2002-2016
Oak Ridge National Laboratory
2015
A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark Uncertainty Analysis in Modeling (UAM) is defined order to facilitate the development validation of available uncertainty analysis sensitivity methods best-estimate Light water Reactor (LWR) design safety calculations. The has been named OECD/NEA UAM-LWR benchmark, divided into three phases each which focuses on a different portion propagation LWR multi-physics multi-scale analysis. Several...
This paper provides a review of current and upcoming innovations in development, validation, uncertainty quantification nuclear reactor multi-physics simulation methods. Multi-physics modelling simulations (M&S) provide more accurate realistic predictions the reactors behavior including local safety parameters. M&S tools can be subdivided two groups: traditional on assembly/channel spatial scale (currently used industry regulation), novel high-fidelity pin (sub-pin)/sub-channel...
The Pennsylvania State University (PSU) under the sponsorship of US Nuclear Regulatory Commission (NRC) has prepared, organized, conducted, and summarized Organisation for Economic Co-operation Development/US (OECD/NRC) benchmark based on Power Engineering Corporation (NUPEC) pressurized water reactor (PWR) subchannel bundle tests (PSBTs). international activities have been conducted in cooperation with Energy Agency (NEA) OECD Japan Safety Organization (JNES), Japan. OECD/NRC PSBT was...