Dr. Jason Hou
Assistant Professor
Director of Reactor Dynamics and Fuel Modeling Group
Department of Nuclear Engineering
North Carolina State University

Abstract

The best estimate plus uncertainty (BEPU) method has been widely utilized to analyze various transient scenarios of nuclear reactors with the aid of multi-physics modeling and simulation (M&S) capabilities. In most BEPU approaches, various uncertain input parameters, either in a single physics or from different physics domains, are considered independent from each other and so are their impact on the uncertainty of system responses. This approach can introduce bias because the input uncertainties may originate from the same fundamental source and thus are in fact correlated with each other. Efforts are being made in the Reactor Dynamics and Fuel Modeling Group (RDFMG) at NC State University to develop and implement a methodology to consistently propagate uncertainties through the multi-step M&S procedure. This talk will highlight two recent projects under this topic, one for light water reactors (LWRs) application and the other for advanced reactors (ARs) application.

Biography

Dr. Jason Hou is an Assistant Professor of Nuclear Engineering at North Carolina State University. Prior to coming to North Carolina State University, he was a postdoctoral scholar in the Department of Nuclear Engineering at University of California, Berkeley. He holds Ph.D. and Master of Science degrees in Nuclear Engineering from Pennsylvania State University and University of Michigan, respectively. He received the Bachelor of Science degree in Engineering Physics from Tsinghua University, China.

His area of research interest includes multi-physics reactor simulation, advanced reactors, fuel cycle analysis, uncertainty quantification, machine learning in engineering applications, and nuclear power plant simulator. Presently he performs studies on the Hi2Lo informing scheme for multi-physics simulation, sensitivity and uncertainty (S/U) analysis in modeling of various reactor systems, high-fidelity reactor core simulator, hybrid Monte Carlo (MC) and deterministic method for core calculations, machine learning for plant prognosis and diagnosis. He is the coordinator of the NEA/OECD homogenization-free time-dependent neutron transport benchmark (C5G7-TD).

Dr. Hou is the Director of Reactor Dynamics and Fuel Modeling Group (RDFMG). He also serves as the Coordinator of the Nuclear Simulation Laboratory.

Thursday, January 21. 2021
4:00 pm seminar
https://ncsu.zoom.us/j/98998854760