1. 中文

Deng Chengcheng

Time:December 22, 2021 Editor:Tang Shiqing Source:

 


Associate Professor


Phone: (+86)27-87559470

Email: dengcc@hust.edu.cn

Academic Areas: Nuclear Engineering

Research Interests: Nuclear Safety, Thermal Hydraulics, Code Validation

 

Academic Degrees

PhD, 2014, Institute of nuclear energy and new energy technology, Tsinghua University, Beijing, China;

Bachelor, 2009, School of nuclear science and technology, Harbin Engineering University, Harbin, China.

 

Professional Experience

Associate Professor (2020-present); School of energy and power engineering, Huazhong University of Science and Technology;

Lecturer (2014-2020); School of energy and power engineering, Huazhong University of Science and Technology.

 

Selected Publications

·     1. Chengcheng Deng, Xueyan Zhang, Ye Yang, Jun Yang*. Research on scaling design and applicability evaluation of integral thermal-hydraulic test facilities: A review, Annals of Nuclear Energy, 131: 273-290, 2019.

·     2. Chengcheng Deng, Lian Chen, Jun Yang, Qiao Wu. Best-estimate calculation plus uncertainty analysis of SBLOCA transient for the scale-down passive test facility, Progress in Nuclear Energy, 112: 191-201, 2019.

·     3. Chengcheng Deng, Yuwen Huang, Meng An, Nuo Yang*. Phonon weak couplings model and its applications: A revisit to two-temperature non-equilibrium transport, Materials Today Physics, 16,100305,2020.

·     4. Chengcheng Deng, Huajian Chang, Benke Qin, Qiao Wu. Stored energy analysis in the scaled-down test facilities, Annals of Nuclear Energy, 96:19-25, 2016.

·     5. Chengcheng Deng, Huajian Chang, Weili Liu, Qiao Wu. Uncertainty analysis using Beta-Bayesian approach in nuclear safety code validation, Annals of Nuclear Energy, 8(70):103-108, 2014.

 

Awards:

Excellent Head Teacher

Second Prize in Teaching Competition

Second Prize of Teaching Quality

 

Courses Taught

Safety of Nuclear Power Plant

Virtual Simulation Experiment of Nuclear Power

 

Projects

·     National Natural Science Foundation of China51606072, The optimization of interfacial thermal conductance and heat transport mechanism under irradiation environment of silicon carbide composites for nuclear applications, 2017/01—2019/12.

·     Sub-project of National Key Research & Development Plan: Collation and verification of severe accident experimental database, 2020/11—2022/11.

·     Horizontal Cooperation Project of China Nuclear Power Research and Design Institute: Research on statistical analysis code framework and key theoretical models, 2021/03—2022/07.

·     National Defense Pre-research Project: Research on scaling and uncertainty analysis of accident models, 2019/01—2020/12.

 


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