Kaiyue Zeng

kzeng2

Graduate Research Assistant

North Carolina State University
Burlington Engineering Lab 1222
Raleigh, NC | 27695-7909
kzeng2@ncsu.edu

Projects:

1) Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors.

2) Multi-objective Core Optimization Study of a Sodium-Cooled Fast Reactor.

3) Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium Fast Reactors.

4) Development of a New Contact Angle Control Algorithm for Level-Set Method.

Education:

PhD. Candidate in Nuclear Engineering, North Carolina State University
Master in Nuclear Engineering, North Carolina State University
Bachelor in Nuclear Engineering, Huazhong University of Science and Technology

Affiliations:

American Nuclear Society

Publications:

[1] K. Zeng, J. Hou, and K. Ivanov, “Uncertainty Analysis of Pressurized Water Reactor Core Cycle Depletion Calculation”, ANS Winter Meeting, Washington DC, USA, 2019.

[2] K. Zeng, N. Stauff, and J. Hou, “Sensitivity and Uncertainty Analysis of the Advanced Burner Reactor Core Using NEAMS Workbench,” ANS Winter Meeting, Washington DC, USA, 2019.

[3] K. Zeng, N. Stauff, J. Hou, and T. Kim, “Development of Multi-objective Core Optimization Framework and Application to Sodium-cooled Fast Test Reactors,” Progress in Nuclear Energy, 2019.

[4] K. Zeng, J. Hou, K. Ivanov, and M. Jessee, “Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core,” Nuclear Technology, 2019

[5] M. Li, K. Zeng, L. Wonnell, and I. Bolotnov, “Development of a New Contact Angle Control Algorithm for Level-Set Method,” Journal of Fluids Engineering, 2019.

[6] K. Zeng, J. Hou, K. Ivanov, and M. Jessee, “Uncertainty Quantification on Pressurized Water Reactor Coupled Core Simulation Using Stochastic Sampling Method,” Best Estimate Plus Uncertainty 2018, Lucca, Italy.

[7] N. Stauff, K. Zeng, G. Zhang, G. Aliberti, J. Hou, T. Fanning, and T. K. Kim, “Uncertainty Quantification of ABR Transient Safety Analysis – Nuclear Data Uncertainties”, Best Estimate Plus Uncertainty 2018, Lucca, Italy.

[8] G. Zhang, K. Zeng, N. Stauff, J. Hou, and T.H. Fanning, “Status of Uncertainty Quantification of ABR Transient Safety Analyses”, Best Estimate Plus Uncertainty 2018, Lucca, Italy.

[9] K. Zeng, J. Hou, K. Ivanov, and M. Jessee, “Uncertainty Analysis of Light Water Reactor Core Simulations Using Statistic Sampling Method”, M&C 2017 – International Conference on Mathematics &Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, 2017.