[1] Man Cheol Kim and Poong Hyun Seong, Reliability graph with general gates: an intuitive and practical method for system reliability analysis, Reliability Engineering and System Safety, Volume 78, Issue 3, Pages 239-246, December 2002
[2] Yeonsub Jung, Poong Hyun Seong and Man Cheol Kim, A model for computerized procedures based on flowcharts and success logic trees, Reliability Engineering and System Safety, Volume 83, Issue 3, Pages 351-362, March 2004
[3] Man Cheol Kim and Poong Hyun Seong, Erik Hollnagel, A probabilistic approach for determining the control mode in CREAM, Reliability Engineering and System Safety, Volume 91, Issue 2, Pages 191-199, February 2006
[4] Man Cheol Kim and Poong Hyun Seong, An analytic model for situation assessment of nuclear power plant operators based on Bayesian inference, Reliability Engineering and System Safety, Volume 91, Issue 3, Pages 270-282, March 2006
[5] Man Cheol Kim and Poong Hyun Seong, A computational model for knowledge-driven monitoring of nuclear power plant operators based on information theory, Reliability Engineering and System Safety, Volume 91, Issue 3, Pages 283-291, March 2006
[6] Jun Seok Lee, Man Cheol Kim, Poong Hyun Seong, Hyun Gook Kang and Seung Cheol Jang, Evaluation of error detection coverage and fault-tolerance of digital plant protection system in nuclear power plants, Annals of Nuclear Energy, Volume 33, Issue 6, Pages 544-554, April 2006
[7] Man Cheol Kim and Poong Hyun Seong, A computational method for probabilistic safety assessment of I&C systems and human operators in nuclear power plants, Reliability Engineering and System Safety, Volume 91, Issue 5, Pages 580-593, May 2006
[8] Suk Joon Kim, Poong Hyun Seong, Jun Seok Lee, Man Cheol Kim, Hyun Gook Kang and Seung Cheol Jang, A method for evaluating fault coverage using simulated fault injection for digitalized systems in nuclear power plants, Reliability Engineering and System Safety, Volume 91, Issue 5, Pages 614-623, May 2006
[9] Man Cheol Kim, Seung Cheol Jang and Jaejoo Ha, Possibilities and limitations of applying software reliability growth models to safety critical software, Nuclear Engineering and Technology, vol.39, no.2, pp.145-148, April 2007
[10] Man Cheol Kim and Poong Hyun Seong, A method for identifying instrument faults in nuclear power plants possibly leading to wrong situation assessment, Reliability Engineering and System Safety, Volume 93, Issue 2, Pages 316-324, February 2008
[11] Seung Jun Lee, Man Cheol Kim and Poong Hyun Seong, An analytical approach to quantitative effect estimation of operation advisory system based on human cognitive process using the Bayesian belief network, Reliability Engineering and System Safety, Volume 93, Issue 4, Pages 567-577, April 2008
[12] Man Cheol Kim, Jinkyun Park and Wondea Jung, Sentence completeness analysis for improving team communications of safety-critical system operators, Journal of Loss Prevention in the Process Industries, Volume 21, Issue 3, Pages 255-259, May 2008
[13] Hyun Gook Kang, Man Cheol Kim, Seung Jun Lee, Ho Jung Lee, Heung Seop Eom, Jong Gyun Choi and Seung-Cheol Jang, An overview of risk quantification issues for digitalized nuclear power plants using a static fault tree, Nuclear Engineering and Technology, vol.41, no.6, pp.849-858, August 2009
[14] Hyun Gook Kang, Ho Gon Lim, Ho Jung Lee, Man Cheol Kim, Seung Cheol Jang, Input-profile-based software failure probability quantification for safety signal generation systems, Reliability Engineering and System Safety, Volume 94, Issue 10, Pages 1542-1546, October 2009
[15] Man Cheol Kim, Jinkyun Park, Wondea Jung, Hanjeom Kim, Yoon Joong Kim, Development of a standard communication protocol for an emergency situation management in nuclear power plants, Annals of Nuclear Energy, Volume 37, Issue 6, Pages 888-893, June 2010
[16] M. Khalaquzzaman, Hyun Gook Kang, Man Cheol Kim, Poong Hyun Seong, Quantification of unavailability caused by random failures and maintenance human errors in nuclear power plants, Nuclear Engineering and Design, Volume 240, Issue 6, Pages 1606-1613, June 2010
[17] M. Khalaquzzaman, Hyun Gook Kang, Man Cheol Kim, Poong Hyun Seong, A model for estimation of reactor spurious shutdown rate considering maintenance human errors in reactor protection system of nuclear power plants, Nuclear Engineering and Design, Volume 240, Issue 10, Pages 2963-2971, October 2010
[18] Man Cheol Kim and Jinkyun Park, Development of a path model for human-induced unplanned reactor trips in nuclear power plants, Quality and Reliability Engineering International, Volume 27, Issue 2, Pages 141-147, March 2011
[19] M. Khalaquzzaman, Hyun Gook Kang, Man Cheol Kim, Poong Hyun Seong, Optimization of periodic testing frequency of a reactor protection system based on a risk-cost model and public risk perception, Nuclear Engineering and Design, Volume 241, Issue 5, Pages 1538-1547, May 2011
[20] Man Cheol Kim, Reliability block diagram with general gates and its application to system reliability analysis, Annals of Nuclear Energy, Volume 38, Issue 11, Pages 2456-2461, November 2011
[21] Man Cheol Kim and Dong-Wook Jerng, Feasibility analysis of aggressive cooldown in OPR-1000 nuclear power plants, Annals of Nuclear Energy, Volume 68, Pages 89-95, June 2014
[22] Man Cheol Kim and Seung Jun Lee, Important factors affecting fault detection coverage in probabilistic safety assessment of digital instrumentation and control systems, Journal of Nuclear Science and Technology, vol. 51, no. 6, pp.809–817, 2014.
[23] Man Cheol Kim, Insights on Accident Information and System Operations during Fukushima Events, Science and Technology of Nuclear Installations, Volume 2014, Article ID 123240, 12 pages, June 2014
[24] M. Khalaquzzaman,Seung Jun Lee, Man Cheol Kim, Wondea Jung, Estimation of reactor protection system software failure probability considering undetected faults, Nuclear Engineering and Design, vol.280, pp.201-209, December 2014.
[25] Dong-Wook Jerng and Man Cheol Kim, Comparison of two approaches for establishing performance criteria related to Maintenance Rule, Journal of Nuclear Science and Technology, vol.52, no.1, pp.122-130, January 2015.
[26] Man Cheol Kim and Carol S. Smidts, Three suggestions on the definition of terms for the safety and reliability analysis of digital systems, Reliability Engineering and System Safety, vol.135, pp.81-91, March 2015.
[27] Man Cheol Kim, Two viewpoints for software failures and their relation in probabilistic safety assessment of digital instrumentation and control systems, Journal of Nuclear Science and Technology, vol.52, no.4, pp.472-480, April 2015.
[28] Seung Min Lee, Man Cheol Kim, Jong Hyun Kim, and Poong Hyun Seong, Optimization of automation: II. Estimation method of ostracism rate based on the loss of situation awareness of human operators in nuclear power plants, Annals of Nuclear Energy, vol.79, pp.93-100, May 2015.
[29] Seung Min Lee, Jong Hyun Kim, Man Cheol Kim, and Poong Hyun Seong, Optimization of automation: III. Development of optimization method for determining automation rate in nuclear power plants, Annals of Nuclear Energy, vol.95, pp.64-74, September 2016.
[30] Man Cheol Kim, Validation of Spent Nuclear Fuel Nuclide Composition Data Using Percentage Differences and Detailed Analysis, atw - International Journal for Nuclear Power, vol.51, pp.402-408, June 2017.
[31] Man Cheol Kim, Feasibility of shared use of alternative AC diesel generator under dual-unit station blackout, Journal of Nuclear Science and Technology, vol.54, pp.1029-1035, October 2017.
[32] Changkyung Seong, Gyunyoung Heo, Sejin Baek, Ji Woong Yoon, Man Cheol Kim, Analysis of the technical status of multiunit risk assessment in nuclear power plants, Nuclear Engineering and Technology, Volume 50, Issue 3, Pages 319-326, April 2018.
[33] Man Cheol Kim, Jeongil Seo, Wondea Jung, Jong Gyun Choi, Hyun Gook Kang, Seung Jun Lee, Evaluation of effectiveness of fault-tolerant techniques in a digital instrumentation and control system with a fault injection experiment, Nuclear Engineering and Technology, Volume 51, Issue 3, Pages 692-701, June 2019.
[34] Man Cheol Kim, Sang Hoon Han, Variability of plant risk due to variable operator allowable time for aggressive cooldown initiation, Nuclear Engineering and Technology, Volume 51, Issue 5, Pages 1307-1313, August 2019.
[35] Ji Suk Kim, Man Cheol Kim, Consistency issues in quantitative safety goals of nuclear power plants in Korea, Nuclear Engineering and Technology, Volume 51, Issue 7, Pages 1758-1764, Volume 51, Issue 7, Pages 1758-1764, October 2019.
[36] Eunseo So, Man Cheol Kim, Level 1 probabilistic safety assessment of supercritical-CO2-cooled micro modular reactor in conceptual design phase, Nuclear Engineering and Technology, Volume 53, Issue 2, Pages 498-508, February 2021.
[37] Gyun Seob Song and Man Cheol Kim, Mathematical Formulation and Analytic Solutions for Uncertainty Analysis in Probabilistic Safety Assessment of Nuclear Power Plants, Energies, 14(4), 929, 10 February 2021.
[38] Ji Suk Kim and Man Cheol Kim, Development of a Software Tool for Seismic Probabilistic Safety Assessment Quantification with a Sufficiently Large Number of Bins for Enhanced Accuracy, Energies, 14(6), 1677, 17 March 2021.
[39] Man Cheol Kim, Systematic approach and mathematical development for conditional core damage probabilities under station blackout of a nuclear power plant, Reliability Engineering and System Safety, 217, 107969, 2022.
[40] Gyun Seob Song, Man Cheol Kim, Theoretical approach for uncertainty quantification in probabilistic safety assessment using sum of lognormal random variables, Nuclear Engineering and Technology, Volume 54, Issue 6, Pages 2084-2093, June 2022.
[41] Eunseo So, Man Cheol Kim, Application of Chernoff bound to passive system reliability evaluation for probabilistic safety assessment of nuclear power plants, Nuclear Engineering and Technology, Volume 54, Issue 8, Pages 2915-2923, August 2022.
[42] Ji Suk Kim, Man Cheol Kim, Insights gained from applying negate-down during quantification for seismic probabilistic safety assessment, Nuclear Engineering and Technology, Volume 54, Issue 8, Pages 2933-2940, August 2022.
[43] Ji Suk Kim, Sang Hoon Han, Man Cheol Kim, Direct fault-tree modeling of human failure event dependency in probabilistic safety assessment, Nuclear Engineering and Technology, Volume 55, Issue 1, Pages 119-130, January 2023.
[44] Ji Suk Kim, Man Cheol Kim, The effect of the number of subintervals upon the quantification of the seismic probabilistic safety assessment of a nuclear power plant, Nuclear Engineering and Technology, Volume 55, Issue 4, April 2023, Pages 1420-1427.
[45] Man Cheol Kim, Station Blackout Risk of a Nuclear Power Plant with Consideration of Time Dependencies and Common Cause Failures, International Journal of Energy Research, Volume 2023, Article ID 5595417, Aug 2023.
[46] Man Cheol Kim, Rigorous derivation of interfacing system LOCA frequency formulas for probabilistic safety assessment of nuclear power plants, Reliability Engineering & System Safety, Volume 238, October 2023, 109470.
[47] Man Cheol Kim, Comparison of event tree/fault tree and convolution approaches in calculating station blackout risk in a nuclear power plant, Nuclear Engineering and Technology, Volume 56, Issue 1, Pages 141-146, January 2024.
[48] Gyun Seob Song, Man Cheol Kim, Comparison of state-of-knowledge correlation effect associated with lognormal, beta, and gamma uncertainty distributions, Reliability Engineering & System Safety, Volume 245, 110033, May 2024.
[49] Jisuk Kim, Man Cheol Kim,, Impact of representative ground motion level on seismic PSA with the boundary between overestimation and underestimation, Nuclear Engineering and Technology, Volume 57, Issue 11, 103753, November 2025.
[50] Gyun Seob Song, Man Cheol Kim, Dependency assessment in human reliability analysis based on performance shaping factors, Nuclear Engineering and Technology, In Press, 103831, Available online 5 August 2025.