Deokjung Lee, Ph.D.

Affiliations: 
2003 Purdue University, West Lafayette, IN, United States 
Area:
Nuclear Engineering
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"Deokjung Lee"

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Thomas J. Downar grad student 2003 Purdue
 (Convergence analysis of the coarse mesh finite difference method.)
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Publications

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Yu J, Lee H, Kim H, et al. (2020) Coupled Neutronics–Thermal-Hydraulic Simulation of BEAVRS Cycle 1 Depletion by the MCS/CTF Code System Nuclear Technology. 206: 728-742
Cherezov A, Jang J, Lee D. (2020) A PCA compression method for reactor core transient multiphysics simulation Progress in Nuclear Energy. 128: 103441
Khoshahval F, Zhang P, Lee D. (2020) Analysis and comparison of direct inversion and Kalman filter methods for self-powered neutron detector compensation Nuclear Instruments & Methods in Physics Research Section a-Accelerators Spectrometers Detectors and Associated Equipment. 969: 164097
Ebiwonjumi B, Kong C, Zhang P, et al. (2020) Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters Nuclear Engineering and Technology
Jang J, Ebiwonjumi B, Kim W, et al. (2020) Validation of spent nuclear fuel decay heat calculation by a two-step method Nuclear Engineering and Technology
Ta DL, Hong SG, Lee D. (2020) Validation of UNIST Monte Carlo Code MCS for Criticality Safety Calculations with Burnup Credit through MOX Criticality Benchmark Problems Nuclear Engineering and Technology
Setiawan F, Lemaire M, Lee D. (2020) Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS Nuclear Engineering and Technology
Ebiwonjumi B, Lee H, Kim W, et al. (2020) Validation of nuclide depletion capabilities in Monte Carlo code MCS Nuclear Engineering and Technology. 52: 1907-1916
Dos V, Lee H, Jo Y, et al. (2020) Overcoming the challenges of Monte Carlo depletion: Application to a material-testing reactor with the MCS code Nuclear Engineering and Technology. 52: 1881-1895
Lemaire M, Lee H, Zhang P, et al. (2020) Interpretation of two SINBAD photon-leakage benchmarks with nuclear library ENDF/B-VIII.0 and Monte Carlo code MCS Nuclear Engineering and Technology. 52: 1355-1366
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