Lecturer of Nuclear Engineering

Phone: (+86)158-2764-7160

Email: dengcc@hust.edu.cn

Academic Areas: Nuclear Engineering

Research Interests: Nuclear reactor thermal-hydraulics, Scaling analysis and code simulation of nuclear systems, Nuclear safety best-estimate and uncertainty analysis, Multi-scale simulation of nuclear materials

Academic Degrees

Ph.D. in Nuclear Engineering and Technology, 2014, Tsinghua University;

BA in Nuclear Engineering and Technology, 2009, Harbin Engineering University.

Professional Experience

Lecturer (2014-present), School of Energy and Power Engineering, Huazhong University of Science and Technology;

Visiting Scholar(2012-2013), Department of Nuclear Engineering, Oregon State University, USA.

Selected Publications

Papers

1. Deng C., Chang H., Qin B., Wu Q. (2016). "Stored energy analysis in the scaled-down test facilities". Annals of Nuclear Energy, 2016, 96:19-25.

2. Deng C., Chang H., Liu W., Wu Q. (2014). "Uncertainty analysis using Beta-Bayesian approach in nuclear safety code validation". Annals of Nuclear Energy, 2014, 8(70):103-108.

3. Liao Q., Liu Z., Liu W., Deng C., Yang N. (2015). "Extremely high thermal conductivity of aligned carbon nanotube-polyethylene composites". Scientific Reports, 2015, 5(16543).

4. Deng C., Chang H., Cheng L. (2016)."Uncertainty and sensitivity analysis of SBLOCA best-estimate calculation". Atomic Energy Science and Technology, 2016, 7(50):1224-1231.

5. Deng C., Yang N., Zou J. (2015). "Molecular dynamics simulation of thermal conductivity of silicon carbide for nuclear applications ". The Seventh Symposium on Nuclear Reactor Physics and Nuclear Materials, Xi'an, 2015.

6. Deng C., Chang H., Qin B., Ye Z., Fang F. (2013). "Stored energy analysis in scaled-down test facility". Atomic Energy Science and Technology, 2013, 10(47):1751-1759.

7. Deng C., Chang H., Qin B., Wang H. (2013). "CMT scaling analysis and distortion evaluation in passive integral test facilities". Atomic Energy Science and Technology, 2013, 11(47):2026-2032.

8. Deng C., Chang H., Chen L., Wu Q. (2014). "Uncertainty and sensitivity analysis of small break loss of coolant accident for the ACME test facility". ANS Winter Meeting and Nuclear Expo, Washington D.C., USA, 2014.

9. Deng C., Liu W., Hallee B., Wu Q. (2013). "Efficient uncertainty analysis using Beta-Bayesian approach". ASME Verification & Validation Symposium, Las Vegas, USA, 2013.

10. Deng C., Chang H., Liu W., Wu Q. (2013). "Uncertainty analysis using Beta-Bayesian approach in nuclear safety code validation".  ANS Winter Meeting and Nuclear Expo, Washington D.C., USA, 2013.

11. Deng C., Chang H., Qin B., Wang H., Chen L. (2012). "Scaling analysis of the pressurizer surge line in nuclear plant integral test facilities". Proceedings of the 20th ICONE, California, USA, 2012.

12. Xue R., Deng C., Li C., Wang M. (2012). "Numerical simulation of shell-side heat transfer and flow of natural circulation heat exchange". Atomic Energy Science and Technology, 2012, 2(46):192-198.

13. Xue R., Deng C., Peng M. (2010). "Numerical Simulation of Passive Residual Heat Removal Heat Exchanger". Atomic Energy Science and Technology, 2010, 4(44):429-435.

Awards and Honors

1. University Excellent Teaching Prize, the second prize, Huazhong University of Science and Technology, 2015.

Courses Taught

0824041: Two phase flow in the energy system (BA course)

0841542: Nuclear Plants Operation Principle (BA course)

Project

1. National Natural Science Foundation of China (Project No. 51606072), “The optimization of interfacial thermal conductance and heat transport mechanism under irradiation environment of silicon carbide composites for nuclear application”, January 1, 2017 to December 31, 2019, Principal Investigator.

2. University Self-innovation Foundation, "Multi-scale simulations of thermal properties of nuclear materials", January 2015 to January 2017, Principal Investigator.

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