Kaichao Sun

Kaichao Sun
Kaichao
Sun
Group Lead, Reactor Physics Analysis
Reactor Engineer, MITR Operation
617-253-2099
NW13-241

Education

Ph.D. Swiss Federal Institute of Technology, Switzerland, Nuclear Engineering, 2012
Paul Scherrer Institute, Switzerland, 2012
M.S. Royal Institute of Technology, Sweden, Nuclear Engineering, 2008
B.S. Tsinghua University, China, Engineering Physics, 2006

Research Interests

  • Nuclear Fuel Cycle and Code Development
  • Reactor Licensing and Safety Analysis
  • Reactor Physics Code Verification and Validation (V&V)
  •  In-core Experiment Design and Safety Evaluation
  • Low Enrichment Uranium (LEU) Core Conversion
  • Advanced and Innovative Test Reactor Design

Patents

European Patent No. 11196146.2–2208. A wrapper tube for a fuel subassembly of a nuclear reactor core and method for protecting fuel against overheating in case of coolant boiling. (Filed in 2011)

Selected Publications

K. Sun, L. Hu, C. Forsberg. Neutronic design features of a transportable Fluoride-salt-cooled High-temperature Reactor. Journal of Nuclear Engineering and Radiation Science (in press) 2016.

C. Wang, K. Sun, L. Hu, S. Qiu, G. Su. Thermal-hydraulic analyses of transportable Fluoride-salt-cooled High-temperature Reactor with CFD modeling. Nuclear Technology (in press) 2016.

K. Sun, D. Carpenter, G. Kohse, L. Hu. Investigation on mitigating neutron streaming effect for the water-loop facility used in the MIT reactor. Progress in Nuclear Energy, vol. 80: pp/ 37-44, 2015.

W. Cheng, K. Sun, L. Hu, C. Chieng. Computational fluid dynamics analysis for asymmetric power generation in a prismatic fuel block of Fluoride-salt-cooled High-temperature Test Reactor. Journal of Nuclear Engineering and Radiation Science, vol. 1 / 011003-1, 2015.

K. Sun, M. Ames, T. Newton, L. Hu. Validation of a fuel management code MCODE-FM against fission product poisoning and flux wire measurement of the MIT Reactor. Progress in Nuclear Energy, vol. 75: pp. 42-48, 2014.

K. Sun, A. Chenu, J. Krepel, K. Mikityuk, R. Chawla. Coupled 3D-neutronics / thermal-hydraulics optimization study for improving the response of a 3600 MWth SFR core to an unprotected loss-of-flow accident. Nuclear Technology, vol. 183: pp. 484-503, 2013.

K. Sun, J. Krepel, K. Mikityuk, R. Chawla, A neutronics study for improving the safety and performance parameters of a 3600 MWth sodium-cooled fast reactor. Annals of Nuclear Energy, vol. 53: pp. 464-475, 2013.

K. Sun, J. Krepel, K. Mikityuk, S. Pelloni, R. Chawla. Void reactivity decomposition for sodium-cooled fast reactor in equilibrium fuel cycle. Annals of Nuclear Energy, vol. 38: pp. 1645-1657, 2011.

Awards

  • European Nuclear Education Network (ENEN) Prize, 2012.
  • Chinese Government Award for outstanding self-financed students abroad, 2012.
  • Best 3rd year PhD Paper, Nuclear Energy and Safety Research Department, PSI, Switzerland, 2011.
  • Scientific Scholarship of Tongfangweishi, Tsinghua University, China, 2003.