Yunzhao Li Associate Professor Nuclear Science and Technology Xi'an Jiaotong University
28 West Xianning Road, Xi'an, Shaanxi 710049 Nuclear Science and Technology Xi'an Jiaotong University Email：yunzhao@xjtu.edu.cn Tel：(+86) 029 8266 8692 Fax：(+86) 029 8266 7802
Asso. Prof. in Nuclear Science and Technology, Xi'an Jiaotong Univ., 2016.1 to present Lecturer in Nuclear Science and Technology, Xi'an Jiaotong Univ., 2013.32015.12 Visiting PreDoctoral Fellow, 2010.102012.9 Department of Mechanical Engineering, Northwestern University Nuclear Engineering Division, Argonne National Laboratory
Ph.D in Nuclear Science and Technology, Xi’an Jiaotong Univ., 2007.9 – 2013.3 B.S. in Nuclear Engineering and Nuclear Technology, Xi’an Jiaotong Univ., 2003.9 – 2007.7

Nuclear Physics, Undergranduates Nuclear Reacotr Physics, Undergraduates Neutron Diffusion Theory and its Numerical Methods, Graduates Monte Carlo Method and its Application in Nuclear Science, Graduates
Development of PWRcore fuel management calculation code system NECPBamboo PWR twostep/pinbypin core analysis methods Neutronics transport/diffusion theory and its numerical methods Education of Nuclear Reactor Physics
ContinuesEnergy Deterministic NeutronTransport Calculation Method (2020.01 2023.12) The critical tool of nuclear reactor core neutronics analysis is the neutrontransport theory, for which the deterministic methods are widely employed by nuclear power engineering due to its high efficiency and low cost. However, the traditional multigroup approximation is still employed, causing two problems. (1) A neutron spectrum has to be assumed and employed during the multigroup nuclear data library production before knowing the exact definition of the calculation scenario. (2) The resonance selfshielding calculation has to be carried out to modify the microscopic cross sections with the spatial geometry and nuclide composition of the specific scenario, to consider the self and crossshielding effects and the nuclide interference effect. Consequently, in this project, a continuesenergy deterministic neutrontransport calculation method, which has never been investigated before, is proposed to fully eliminate the multigroup approximation. It is planned to expand the smoothly continuous neutron flux in the nonresonance region, the probabilistic neutron flux in the unrecognized resonance region and the oscillatingly continuous neutron flux in the recognized resonance region by using proper orthogonal basis functions. The single and bicoupling relationships between different energy regions have to be carefully considered and the iterative strategies have to be designed. At the end, the entire methodology is planned to be verified and validated by using the measured data from active nuclear power plants. It is believed that this fundamental cuttingedge investigation will not only play a significant scientific role in developing neutrontransport theory, but also provide a better innovation perspective for nuclearpower software autonomy.
Research on the Key Techniques of Pinbypin PWR Incore Fuel Manangement Calculation (2018.01 2021.12) PWR incore fuel management calculation provides pinbypin power distribution for safety and economy analysis of the corresponding reactor core by simulating the multiphysics coupling process including neutronics, thermalhydraulics and nuclide depletion, et al. However, there are too more approximations in the current incore fuel management calculation, which limits the safety and economic characteristics of the PWR reactor core through calculation accuracy. Consequently, based on the research foundation in our team, the pinbypin incore fuel management calculation method, which is as the most possible next generation method, is proposed to be investigated mainly on its key techniques including: (1) heterogeneous leakage model for pinbypin homogenization, (2) pincell homogenized fewgroup constants parameterization, and (3) multiphysics coupling technique in threedimensional whole core pinbypin calculation. Under the background of "Go Global" strategy, the research of this project is of important academic significance for the development and perfection of PWR core analysis theory, and is also a key step in the independent innovation of nuclear power softwares. Thus, it is a frontier basic research.
[1]. Yunzhao Li, Boning Liang, Hongchun Wu, Zhipeng Li and Jiewei Yang. Heterogeneous discontinuity factor treatment in Variational Nodal Method. Ann. Nucl. Energy, 127:341350, 2019. [2]. Yunzhao Li, Bin Zhang, Qingming He, Dongyong Wang, Hongchun Wu, Liangzhi Cao and Wei Shen. Development and verification of PWRcore fuel management calculation code system NECPBamboo: Part I BambooLattice. Nucl. Eng. Des., 2018, 335:432440. [3]. Yunzhao Li, Zhipeng Li, Hongchun Wu and Youqi Zheng. Improved Variational Nodal Method Based on Symmetry Group Theory, Nucl. Sci. Eng., 190:134155, 2018. [4]. Yunzhao Li, Bin Zhang, Hongchun Wu and Wei Shen. Heterogeneous neutronleakage model for PWR pinbypin calculation. Ann. Nucl. Energy, 110:443452, 2017. [5]. Jie Li, Yunzhao Li, Qi Zheng, Wei Shen. A weighted Monte Carlo solution of the neutron kinetics equations. M&C2017, Jeju, Korea, April 1520, 2017. [6]. Yunzhao Li, Kai Huang, Hongchun Wu, Liangzhi Cao. A depletion system compression method based on quantitative significance analysis. Nucl. Sci. Eng. 187(1):4969, 2017.
