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Hyung Jin Shim

Observed names: H. J. Shim, H. Shim, HYUNG JIN SHIM, Hyung Jin SHIM, Hyung-Jin SHIM, Hyung-Jin Shim
ORCID: 0000-0001-5745-1919
Observed ORCID: 0000-0001-5745-1919
OpenAlex ID: A5082262730
Mccard: Monte Carlo Code for Advanced Reactor Design and Analysis
2012 · Hyung-Jin Shim, Beom-Seok Han, et al. · Nuclear Engineering and Technology · 159
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Adjoint Sensitivity and Uncertainty Analyses in Monte Carlo Forward Calculations
2011 · Hyung Jin SHIM, Chang Hyo KIM · Journal of Nuclear Science and Technology · 69
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Generation of Few-Group Diffusion Theory Constants by Monte Carlo Code McCARD
2012 · Ho Jin Park, Hyung Jin Shim, et al. · Nuclear Science and Engineering · 45
Whole Core Transport Calculation Employing Hexagonal Modular Ray Tracing and CMFD Formulation
2008 · Jin-Young CHO, Kang-Seog KIM, et al. · Journal of Nuclear Science and Technology · 40
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Dynamic Monte Carlo transient analysis for the Organization for Economic Co-operation and Development Nuclear Energy Agency (OECD/NEA) C5G7-TD benchmark
2017 · Nadeem Shaukat, Min Ryu, et al. · Nuclear Engineering and Technology · 35
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Real Variance Estimation Using an Intercycle Fission Source Correlation for Monte Carlo Eigenvalue Calculations
2009 · Hyung Jin Shim, Chang Hyo Kim · Nuclear Science and Engineering · 34
Uncertainty Propagation in Monte Carlo Depletion Analysis
2011 · Ho Jin Park, Hyung Jin Shim, et al. · Nuclear Science and Engineering · 31
Stopping Criteria of Inactive Cycle Monte Carlo Calculations
2007 · Hyung Jin Shim, Chang Hyo Kim · Nuclear Science and Engineering · 25
Memory-efficient calculations of adjoint-weighted tallies by the Monte Carlo Wielandt method
2016 · Sung Hoon Choi, Hyung Jin Shim · Annals of Nuclear Energy · 21
Development of Generalized Perturbation Theory Algorithms for Monte Carlo Eigenvalue Calculations
2017 · Sung Hoon Choi, Hyung Jin Shim, et al. · Nuclear Science and Engineering · 20
Real variance analysis of Monte Carlo eigenvalue calculation by McCARD for BEAVRS benchmark
2015 · Ho Jin Park, Hyun Chul Lee, et al. · Annals of Nuclear Energy · 17
Decay heat analysis of VHTR cores by Monte Carlo core depletion calculation
2010 · Hyun Chul Lee, Chang Keun Jo, et al. · Annals of Nuclear Energy · 16
Optimization layer by layer networks for in-core fuel management optimization computations in PWRs
2001 · Chang Sun Jang, Hyung Jin Shim, et al. · Annals of Nuclear Energy · 16
Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD
2018 · Ho Jin Park, Dong Hyuk Lee, et al. · Nuclear Engineering and Technology · 15
Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysis
2015 · Hyung Jin Shim, Sang Hoon Jang, et al. · Science and Technology of Nuclear Installations · 15
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Real Variance Estimation by Grouping Histories in Monte Carlo Eigenvalue Calculations
2014 · Hyung Jin Shim, Sung Hoon Choi, et al. · Nuclear Science and Engineering · 13
Parallel Computing Adaptive Simulated Annealing Scheme for Fuel Assembly Loading Pattern Optimization in PWRs
2001 · Hyun Chul Lee, Hyung Jin Shim, et al. · Nuclear Technology · 13
Advances for the time-dependent Monte Carlo neutron transport analysis in McCARD
2023 · Sang Hoon Jang, Hyung Jin Shim · Nuclear Engineering and Technology · 12
Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis
2015 · Seung Yeol Yoo, Hyung Jin Shim, et al. · Science and Technology of Nuclear Installations · 12
Tally efficiency analysis for Monte Carlo Wielandt method
2009 · Hyung Jin Shim, Chang Hyo Kim · Annals of Nuclear Energy · 11
Uncertainty Propagation Analysis for PWR Burnup Pin-Cell Benchmark by Monte Carlo Code McCARD
2012 · Ho Jin Park, Hyung Jin Shim, et al. · Science and Technology of Nuclear Installations · 10
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Effect of Cross Section Uncertainties on Criticality Benchmark Problem Analysis by MCCARD
2011 · H. J. Shim, H. G. Joo, et al. · Journal of the Korean Physical Society · 10
Monte Carlo Fuel Temperature Coefficient Estimation by an Adjoint-Weighted Correlated Sampling Method
2014 · Hyung Jin Shim, Chang Hyo Kim · Nuclear Science and Engineering · 9
Development of deep convolutional neural network for prediction of cycle maximum pin power peaking factor in pressurized water reactor
2023 · Younduk Nam, Hyung Jin Shim · Annals of Nuclear Energy · 8
Verification of the nTRACER/CTF code system for full core high resolution cycle analysis with the OECD/NEA TVA Watts Bar Unit 1 benchmark
2025 · Sung Joon Kwon, Marianna Papadionysiou, et al. · Annals of Nuclear Energy · 7
Works count: 66
Citation count: 736
H-index: 15
I10-index: 22
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