Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation (Woodhead Publishing Series in Energy) - Softcover

Über die Autorinnen und Autoren

Prof. Liangzhi Cao earned his PhD in Nuclear Engineering from Xi’an Jiaotong University (XJTU) in 2005, after which he work there as a faculty member in the School of Nuclear Science and Technology.
Prof. Cao is now serving as the Executive Editor of Annals of Nuclear Energy, Associate Editor of ASME J. of Nuclear Engineering and Radiation Science, the Program Committee member of Reactor Physics Division of ANS. He won a Second Prize of National Technological Invention of China in 2019 and was awarded the ICONE Long Service Award in 2021 by ASME. Prof. Cao is well known for his work in the field of reactor physics, including the resonance self-shielding methods, neutron-transport methods, sensitivity and uncertainty analysis, and code verification and validation, etc. He has authored more than 200 journal papers, co-authored two monographs in reactor physics analysis methods.

Prof. Hongchun Wu is one of the most leading professors in reactor physics community in China. He received his PhD in 1994 from XJTU, became a full professor of XJTU in 2001. He is the committee member of Chinese Nuclear Society (CNS) and the Chief Scientist of China’s 863 Project. He also serves as the member of the Subject Consultative Group of the State Council, the academic committee member of the National-level Key Laboratory for Reactor-system Design. Prof. Wu is now leading several key research projects funded by the Minister of Science and Technology of China and Natural Science Foundation of China. Prof. Wu has been focusing on the deterministic transport-calculation methods for several decades, authored more than 100 journal papers, co-authored a book, graduated 30 PhD students and 45 Master students in reactor physics.

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Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation presents the latest deterministic numerical methods for neutron transport equations (NTEs) with complex geometry, which are of great demand in recent years due to the rapid development of advanced nuclear reactor concepts and high-performance computational technologies. This book covers the wellknown methods proposed and used in recent years, not only theoretical modeling but also numerical results.

This book provides readers with a very thorough understanding of unstructured neutron transport calculations and enables them to develop their own computational codes. The fundamentals, numerical discretization methods, algorithms, and numerical results are discussed. Researchers and engineers from utilities and research institutes are provided with examples on how to model an advanced nuclear reactor, which they can then apply to their own research projects and lab settings.