Regular biography
HE Donghao is a Faculty member in the School of Mechanical Engineering at Shanghai Jiao Tong University. He is affiliated with the Institute of Nuclear Science and Safety. His research interests are not explicitly detailed in the provided information. His profile page provides contact details, including a website link, but no further specifics on his academic background or achievements are available.
Scholar-generated biography
Donghao He is a researcher at Shanghai Jiaotong University specializing in Radiation Transport Theory. His work focuses on developing and verifying advanced neutron transport methods for reactor physics simulations. He has contributed to the development of the RAPID code, which integrates fission matrix techniques for improved reactor core analysis. His research includes the application of fission matrix correction methods, variational nodal methods, and hybrid algorithms for reactor shielding optimization. He has also worked on coupling neutronics-thermal hydraulics models and uncertainty analysis for reactor simulations. His studies cover both fast and thermal reactors, with applications in small modular reactors and high-fidelity benchmarking.