Jianwei Hu
About Jianwei Hu
Jianwei Hu is an R&D staff member specializing in spent nuclear fuel analysis at Oak Ridge National Laboratory. He has extensive experience in nuclear engineering, having worked at various prestigious institutions and contributed to significant research in isotopic transmutation and fuel cycle concepts.
Current Role at Oak Ridge National Laboratory
Jianwei Hu serves as an R&D staff member for spent nuclear fuel analysis at Oak Ridge National Laboratory. He has held this position since 2013, contributing to the field for 11 years. His work focuses on the analysis of spent nuclear fuel, utilizing advanced modeling techniques to enhance understanding of fuel behavior and performance.
Previous Experience at Los Alamos National Laboratory
Prior to his current role, Jianwei Hu worked at Los Alamos National Laboratory as a Nuclear Engineer (Postdoc) from 2011 to 2012. He also served as a Graduate Research Assistant from 2007 to 2011. His time at Los Alamos involved significant research in nuclear engineering, contributing to various projects related to nuclear fuel analysis.
Education and Academic Background
Jianwei Hu has a robust academic background in Nuclear Engineering. He earned his PhD from the University of Illinois at Urbana-Champaign, where he studied from 2006 to 2011. He also obtained a Master’s degree in the same field from the same institution, studying from 2003 to 2006. His undergraduate studies were completed at Xi'an Jiaotong University, where he received a Bachelor’s degree in Nuclear Engineering from 1997 to 2001.
Research Contributions and Specializations
Jianwei Hu specializes in the modeling of fuel depletion and material activation in light water reactors and advanced reactor fuel designs. He has contributed to the development and benchmark testing of methods for isotopic transmutation, depletion, and decay. His research also includes studies on various nuclear fuel cycle concepts to evaluate isotope transmutation and optimize fuel utilization.
Technical Skills and Tools Utilized
In his research, Jianwei Hu utilizes SCALE/TRITON for spent fuel and source terms characterization. He collaborates with the Nuclear Security Modeling Group to enhance isotopic predictions in nuclear safeguards and nonproliferation research and development, showcasing his technical expertise in nuclear modeling and analysis.