Deokjung Lee

Orcid: 0000-0002-3935-5058

Affiliations:
  • Ulsan National Institute of Science and Technology, South Korea


According to our database1, Deokjung Lee authored at least 16 papers between 2015 and 2023.

Collaborative distances:
  • Dijkstra number2 of four.
  • Erdős number3 of four.

Timeline

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Bibliography

2023
Group constants generation by Monte Carlo code MCS for LWR analysis.
Comput. Phys. Commun., April, 2023

2022
A novel S<sub><i>N</i></sub>/MOC collaborative method for few-group cross-section generation with versatile neutron spectral adaptability in advanced reactor physics analysis.
Comput. Phys. Commun., 2022

2021
Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation.
Comput. Phys. Commun., 2021

Development of high-fidelity neutron transport code STREAM.
Comput. Phys. Commun., 2021

2020
Coupling of FRAPCON for fuel performance analysis in the Monte Carlo code MCS.
Comput. Phys. Commun., 2020

2019
MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON.
Comput. Phys. Commun., 2019

Performance evaluation of CMFD on inter-cycle correlation reduction of Monte Carlo simulation.
Comput. Phys. Commun., 2019

2018
On the Transfer Matrix of the Modified Power Method.
Comput. Phys. Commun., 2018

Verification of photon transport capability of UNIST Monte Carlo code MCS.
Comput. Phys. Commun., 2018

2017
A new approach to three-dimensional neutron transport solution based on the method of characteristics and linear axial approximation.
J. Comput. Phys., 2017

Extension of the noise propagation matrix method for higher mode solutions.
J. Comput. Phys., 2017

Resonance treatment using pin-based pointwise energy slowing-down method.
J. Comput. Phys., 2017

2016
Extension of modified power method to two-dimensional problems.
J. Comput. Phys., 2016

A general solution strategy of modified power method for higher mode solutions.
J. Comput. Phys., 2016

2015
Convergence analysis of two-node CMFD method for two-group neutron diffusion eigenvalue problem.
J. Comput. Phys., 2015

Impact of inflow transport approximation on light water reactor analysis.
J. Comput. Phys., 2015


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