Basic Info

 

 

Yunzhao Li

Professor

Nuclear Science and Technology

Xi'an Jiaotong University

Contact Info

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

Positions

Prof. in Nuclear Science and Technology, Xi'an Jiaotong Univ., 2020.5 to present

Asso. Prof. in Nuclear Science and Technology, Xi'an Jiaotong Univ., 2016.1-2020.4
Lecturer in Nuclear Science and Technology, Xi'an Jiaotong Univ., 2013.3-2015.12
Visiting Pre-Doctoral Fellow, 2010.10-2012.9
    Department of Mechanical Engineering, Northwestern University

    Nuclear Engineering Division, Argonne National Laboratory

Educations

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

Teaching

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

Research Interests

Development of PWR-core fuel management calculation code system NECP-Bamboo

PWR two-step/pin-by-pin core analysis methods

Neutronics transport/diffusion theory and its numerical methods

Education of Nuclear Reactor Physics

Scientific Research

Continues-Energy Deterministic Neutron-Transport Calculation Method (2020.01- 2023.12)

The critical tool of nuclear reactor core neutronics analysis is the neutron-transport theory, for which the deterministic methods are widely employed by nuclear power engineering due to its high efficiency and low cost. However, the traditional multi-group approximation is still employed, causing two problems. (1) A neutron spectrum has to be assumed and employed during the multi-group nuclear data library production before knowing the exact definition of the calculation scenario. (2) The resonance self-shielding 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 cross-shielding effects and the nuclide interference effect. Consequently, in this project, a continues-energy deterministic neutron-transport calculation method, which has never been investigated before, is proposed to fully eliminate the multi-group approximation. It is planned to expand the smoothly continuous neutron flux in the non-resonance 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 bi-coupling 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 cutting-edge investigation will not only play a significant scientific role in developing neutron-transport theory, but also provide a better innovation perspective for nuclear-power software autonomy.


Research on the Key Techniques of Pin-by-pin PWR In-core Fuel Manangement Calculation (2018.01- 2021.12)

PWR in-core fuel management calculation provides pin-by-pin power distribution for safety and economy analysis of the corresponding reactor core by simulating the multi-physics coupling process including neutronics, thermal-hydraulics and nuclide depletion, et al. However, there are too more approximations in the current in-core 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 pin-by-pin in-core 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 pin-by-pin homogenization, (2) pin-cell homogenized few-group constants parameterization, and (3) multi-physics coupling technique in three-dimensional whole core pin-by-pin 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.

Recent Publications

[01]. Yunzhao Li*, Wen Yang, Sicheng Wang, et al. A Three-dimensional PWR-core pin-by-pin analysis code NECP-Bamboo2.0. Annals of Nuclear Energy, 144, 2020.

[02]. Jie Li, Yunzhao Li*, Wei Shen, et al. Monte Carlo Neutron-Kinetics Analysis in Continuous Time and Energy. Annals of Nuclear Energy, 141, 2020.

[03]. Yunzhao Li*, Tao He, Boning Liang, et al. Development and verification of PWR-core nuclear design code system NECP-Bamboo: Part III: Bamboo-Transient. Nuclear Engineering and Design, 359, 2020.

[04]. Guowei Hua, Yunzhao Li* and Sicheng Wang. PWR pin-homogenized cross-sections analysis using big-data technology. Progress in Nuclear Energy, 121, 2020.

[05]. Qi Zheng, Wei Shen, Yunzhao Li*, et al. A deterministic-stochastic energy-hybrid method for neutron-transport calculation. Annals of Nuclear Energy, 128:292-299, 2019.

[06]. Yunzhao Li*, Boning Liang, Hongchun Wu, et al. Heterogeneous discontinuity factor treatment in Variational Nodal Method. Annals of Nuclear Energy, 127:341-350, 2019.

[07]. Wen Yang, Hongchun Wu, Yunzhao Li*, et al. Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core. Nuclear Engineering and Design, 337:279-290, 2018.

[08]. Yunzhao Li*, Bin Zhang, Qingming He, et al. Development and Verification of PWR-Core Fuel Management Calculation Code System NECP-Bamboo: Part I Bamboo-Lattice. Nuclear Engineering and Design, 335:432-440, 2018.

[09]. Yunzhao Li*, Zhipeng Li, Hongchun Wu, et al. Improved Variational Nodal Method Based on Symmetry Group Theory, Nuclear Science and Engineering, 190:134-155, 2018.

[10]. Wen Yang, Hongchun Wu, Yunzhao Li*, et al. Acceleration of the exponential function expansion nodal SP3 method by multi-group GMRES algorithm for PWR pin-by-pin calculation. Annals of Nuclear Energy, 120:869-879, 2018.

[11]. Boning Liang, Hongchun Wu and Yunzhao Li*. Adaptive expansion order for diffusion Variational Nodal Method. Annals of Nuclear Energy, 117:114-130, 2018.

[12]. Zhitao Xu, Hongchun Wu and Yunzhao Li*, et al. Improved discrete nodal transport method for treating void regions. Annals of Nuclear Energy, 108:172-180, 2018.

[13]. Yunzhao Li*, Bin Zhang, Hongchun Wu, et al. Heterogeneous neutron-leakage model for PWR pin-by-pin calculation. Annals of Nuclear Energy, 110:443-452, 2017.

[14]. Bin Zhang, Hongchun Wu, Yunzhao Li*, et al. Evaluation of Pin-Cell Homogenization Techniques for PWR Pin-by-Pin Calculation. Nuclear Science and Engineering, 186:134-146, 2017.

[15]. Zhipeng Li, Hongchun Wu, Yunzhao Li*, et al. Block-diagonalization of the variational nodal response matrix using the symmetry group theory. Journal of Computational Physics, 351:230-253, 2017.

[16]. Kai Huang, Hongchun Wu, Yunzhao Li*, et al. Depletion system compression method with treatment of decay heat. Progress in Nuclear Energy. 101:476-485, 2017.

[17]. Yongping Wang, Hongchun Wu and Yunzhao Li*. Comparison of two three-dimensional heterogeneous variational nodal methods for PWR control rod cusping effect and pin-by-pin calculation. Progress of Nuclear Energy, 101:370-380, 2017.

[18]. Yongping Wang, Hongchun Wu, Yunzhao Li*, et al. Investigation on generalized Variational Nodal Methods for heterogeneous nodes. Annals of Nuclear Energy. 101:36-48, 2017.

[19]. Yunzhao Li*, Kai Huang, Hongchun Wu, Liangzhi Cao. A depletion system compression method based on quantitative significance analysis. Nuclear Science and Engineering. 187(1):49-69, 2017.

[20]. Zhuo Li, Liangzhi Cao, Hongchun Wu, Yunzhao Li*, et al. Development and validation of a PWR on-line power-distribution monitoring system NECP-ONION. Nuclear Engineering and Design, 322:104-115, 2017.

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