EDUCATION

Ph.D. in Nuclear Engineering, Seoul National University, 2011

• Focused on few group constants generation for two-step procedure based on Monte Carlo method and uncertainty propagation analysis in B1 calculations

•  Finished with Thesis, “Generation of Assembly-Homogenized Few Group Constants and Estimation of Their Uncertainties by Monte Carlo Method”

B.S. in Nuclear Engineering and Computer Science, Seoul National University, Seoul, Korea, 2004

• Focused on sensitivity analysis for critical facility with various evaluated nuclear data libraries – ENDF/B, JENDL, JEFF

• Finished with Thesis, “Analysis of Critical Facility by Monte Carlo Method”

PROFESSIONAL EXPERIENCE

01/2022-present ASSOCIATE PROFESSOR, Kyung Hee University (KHU)

Research on Monte Carlo method and reactor physics

Development of high fidelity and performance Monte Carlo transport code

Utilization in education and training for AGN-201K critical facility

01/2025-present DIRECTOR, Kyung Hee University (KHU) Reactor Research and Education Center (RREC) 

01/2022-12/2024 EXPERT COMMUITTEEMAN, Kyung Hee University (KHU) Reactor Research and Education Center (RREC) 

12/2011-12/2021 SENIOR RESEARCHER, Korea Atomic Energy Research Institute (KAERI)

Research on Monte Carlo method for nuclear reactor design analysis.

Research on sensitivity and uncertainty analysis based on Monte Carlo method.

Management and Improvement of KAERI library generation system for lattice code.

Project Manager for South Korea-Saudi international cooperation project (SMART NNL)

09/2013-12/2013 VISITING SCHOLAR, Oak Ridge National Laboratory (ORNL)

Application of probability table method in unresolved energy region for SCALE.

Improvement of KAERI library generation code system.

04/2011-12/2011 RESEARCHER, Center for Advanced Research in Fusion Reactor Engineering (CARFRE)

09/2005-08/2006 ASSISTANT, Department of Nuclear Engineering, Seoul National University (SNU)

09/2014-09/2016 GENERAL AFFAIRS, McCARD User Group

RESEARCH INTERESTS

Monte Carlo Nuclear Analysis Methodology, Few Group Constants Generation Methodology by Monte Carlo Analysis, Library Generation Processing for Lattice Code, Uncertainty Propagation Analysis, Sensitivity and Uncertainty Analysis, Real Variance Estimation in Monte Carlo Eigenvalue Calculations, Monte Carlo Burnup Analysis, Multi-physics Code Coupling, Similarity Analysis, Reactor Physics Experiment. Subcriticality.

DEVELOPED CODES

McCARD: Monte Carlo code for neutronics analysis of nuclear reactor system (Co-author)

ROULLETE: Multi-group Monte Carlo code (1st author)

MIG: Code input generator program for library generation and S&U analysis (1st author)

MOCHA: Output convertor program for few group constants generation (1st author)

CORRIT: Program for Resonance Integral Correction using SPH Factor (1st author)

CORRXS: Program for Multi-group Cross Section Correction using SPH Factor (1st author)

SIMTEST: Similarity Coefficient Generation Code (1st author)

PUBLICATION (86)

A. Journal (21)

 A-1 Jeongwoo Park and Ho Jin Park, “AGN-201K educational and research reactor benchmark analyses by McCARD Monte Carlo calculations,” Nuclear Engineering and Technology, Vol. 57, 103234, (2025).

A-2 Ho Jin Park and Seung-Ah Yang, “Fission source convergence diagnosis in Monte Carlo eigenvalue calculations by skewness and kurtosis estimation methods,” Nuclear Engineering and Technology, Vol. 56, pp. 3775-3784, September (2024).

A-3 Ho Jin Park and Jeongwoo Park, “Similarity Coefficient Generation Using Adjoint-Based Sensitivity and Uncertainty Method and Stochastic Sampling Method,” Energies, Vol. 17, 827, February (2024).

A-4 Ho Jin Park and Jin Young Cho, “Establishment of DeCART/MIG stochastic sampling code system and Application to UAM and BEAVRS benchmarks,” Nuclear Engineering and Technology, Vol. 55, pp. 1563-1570, April (2023).

A-5 Ho Jin Park, “McCARD/MIG Stochastic sampling calculations for nuclear cross section sensitivity and uncertainty analysis,” Nuclear Engineering and Technology, Vol 54, pp 4272-4279, November (2022).

A-6 Ho Jin Park, Mohammad Alosaimi, Seung-Ah Yang, Heejeong Jeong, Sung Hoon Choi, “McCARD Criticality Benchmark Analyses with Various Evaluated Nuclear Data Libraries,” Energies, Vol. 15, 6852, September (2022).

A-7 Ho Jin Park and Jin Young Cho, “Critical Buckling Generation of TCA Benchmark by the B1Theory-Augmented Monte Carlo Calculation and Estimation of Uncertainties,” Energies, Vol. 14, 2578, April (2021).

A-8 Ho Jin Park, Seong Jin Kim, Hyuk Kwon, Jin Young Cho, “BEAVRS benchmark analyses by DeCART stand-alone calculations and comparison with DeCART/MATRA multi-physics coupling calculations,” Nuclear Engineering and Technology, Vol 52, pp 1896-1906, September (2020).

A-9 Ho Jin Park, Hyunwook Kang, Hyun Chul Lee, Jin Young Cho, “Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 in criticality, depletion benchmark, and uncertainty analyses by McCARD,” Annals of Nuclear Energy, Vol 131, pp 443-459, September (2019).

A-10 Jin Young Cho, Tae Young Han, Ho Jin Park, Ser Gi Hong, Hyun Chul Lee, “Improvement and verification of the DeCART code for HTGR core physics analysis,” Nuclear Engineering and Technology, Vol. 51, pp 13-30, Oct (2019).

A-11 Ho Jin Park, Dong Hyuk Lee, Byoung Kyu Jeon, and Hyung Jin Shim, “Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD,” Nuclear Engineering and Technology, Vol. 50, pp 1043-1050, Oct (2018).

A-12 Ho Jin Park, Kang Seog Kim, Ser Gi Hong, and Jae Seung Song, “An improved DeCART library generation procedure with explicit resonance interference using continuous energy Monte Carlo calculation,” Annals of Nuclear Energy, Vol 105, pp 95-105, July (2017).

A-13 Ho Jin Park, Hyun Chul Lee, Hyung Jin Shim, and Jin Young Cho, “Real variance analysis of Monte Carlo eigenvalue calculation by McCARD for BEAVRS benchmark,” Annals of Nuclear Energy, Vol 90, pp 205-211, April (2016).

A-14 Hyung Jin Shim, Ho Jin Park, Soonwoo Kwon, Geon Ho Seo, and Chang Hyo Kim, “McCARD for Neutronics Design and Analysis of Research Reactor Cores,” Annals of Nuclear Energy, Vol 82, pp 48-53 (2015).

A-15 Ho Jin Park, Dong Hyuk Lee, Hyung Jin Shim, and Chang Hyo Kim, “Uncertainty Propagation Analysis for Yonggwang Nuclear Unit 4 by McCARD/MASTER Core Analysis System,” Nuclear Engineering and Technology, Vol. 46,pp 291-298 (2014).

A-16 Ho Jin Park, Hyung Jin Shim, Han Gyu Joo, and Chang Hyo Kim, “Uncertainty quantification of few-group Diffusion Theory Constants Generated by the B1 Theory-Augmented Monte Carlo Method,” Nuclear Science and Engineering, Vol. 175,pp 28-43 (2013).

A-17 Ho Jin Park, Hyung Jin Shim, and Chang Hyo Kim, “Uncertainty Propagation Analysis for PWR Burnup Pin-Cell Benchmark by Monte Carlo Code McCARD,” Science and Technology of Nuclear Installations, Volume 2012, Article ID 616253 (2012).

A-18 Ho Jin Park, Hyung Jin Shim, and Chang Hyo Kim, “Generation of Few-Group Diffusion Theory Constants by Monte Carlo Code McCARD,” Nuclear Science and Engineering, Vol. 172,pp 66-77 (2012).

A-19 Hyung Jin Shim, Beom Seok Han, Jong Sung Jung, Ho Jin Park, and Chang Hyo Kim, "McCARD: Monte Carlo Code for Advanced Reactor Design and Analysis," Nuclear Engineering and Technology, Vol. 44 No. 2, pp 161-176, (2012).

A-20 Ho Jin Park, Hyung Jin Shim, and Chang Hyo Kim, “Uncertainty Propagation in Monte Carlo Depletion Analysis,” Nuclear Science and Engineering, Vol. 167, pp 196-208 (2011).

A-21 Ho Jin Park, Han Gyu Joo, Hyung Jin Shim, Choong Sup Gil, and Chang Hyo Kim, "Effect of Cross Section Uncertainties on Criticality Benchmark Problem Analysis by McCARD," Journal of the Korean Physical Society, Vol 59 No 2., pp 1251-1255, (2011).

B. Transactions (4)

B-1 Ho Jin Park, Byung Chul Lee, Chang Je Park, Jin Young Cho, “MNR Benchmark Analysis Using McCARD Monte Carlo Code with ENDF/B-VIII.0,” Trans. Am. Nuc. Soc., Vol 119, pp 1069-1070 (2018).

B-2 Ho Jin Park, Hyung Jin Shim, and Chang Hyo Kim, “Uncertainty Quantification in Monte Carlo Criticality Calculations with ENDF/B-VII.1 Covariance Data," Trans. Am. Nuc. Soc., Vol 106, pp 796-797 (2012).

B-3 Ho Jin Park, Hyung Jin Shim, Choong Sub Gil, and Chang Hyo Kim, “Effect of Fission Spectrum Data Uncertainty on Criticality Benchmark Calculations by McCARD,” Trans. Am. Nuc. Soc., Vol 103, pp 397-398, (2010).

B-4 Hyung Jin Shim, Ho Jin Park and Chang Hyo Kim,“Error propagation in Monte Carlo depletion analysis,” Trans. Am. Nuc. Soc., Vol 96., pp 582-584, (2007).

C. International Conference (18)

C-1 Jeong Woo Park and Ho Jin Park, "Multi Cycle Core Follow Calculations for Hanbit Unit 3 using the McCARD/MASTER code system with ENDF/B-VII.1 and ENDF/B-VIII.0 Evaluated Nuclear Data Libraries," International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025), Denvor, CO, USA, April 27-30, (2025).

C-2 Chihun Kim and Ho Jin Park, "DeCART2D Calculations of APR-1400 Benchmark using Improved Cross Section Library Generation System," International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025), Denvor, CO, USA, April 27-30, (2025).

C-3 Ho Jin Park, Jeong Woo Park, Chi Hun Kim, Ji Min Hur, Young Beom Shon, and Myung Hyun Kim, "Preliminary Benchmark Evaluation of AGN-201K Educational and Research Reactor,"Proceedings of the Reactor Physics Asia 2023 (RPHA2023) Conference, Gyeongju, Korea, October 24-26, (2023).

C-4 Ho Jin Park, Jin Young Cho, “BEAVRS Benchmark Analysis by a Whole Core Transport Code nTER,” Proceedings of the Reactor Physics Asia 2019 (RPHA19) Conference, Osaka, Japan, Dec. 2-3, (2019).

C-5 Ho Jin Park, Seong Jin Kim, Hyuk Kwon, Jin Young Cho, “BEAVRS Benchmark Analysis by DeCART Standalone and DeCART/MATRA Multi-Physics Code Coupling Calculations,” ANS M&C 2019, Portland, OR, USA, Aug. 25-29, (2019).

C-6 Jin Young Cho, Seungsu Yuk, Tae Young Han, Young Hee Choi, Ho Jin Park, Hwan Soo Lee, Ho Cheol Shin, “Performance of a Whole Core Transport code, nTER,” The 6th International Conference on Nuclear and Renewable Energy Resources (NURER2018), Ramada Plaza Jeju, Korea, Sep.30-Oct.3, (2018).

C-7 Ho Jin Park and Jin Young Cho, “Generation of Critical Buckling and Estimation of Their Uncertainties by the B1 Theory-Augmented Monte Carlo Method,” PHYSOR 2018: Reactors Physics paving the way towards more efficient systems, Cancun, Mexico, April 22-26, (2018).

C-8 Ho Jin Park, Byoung Kyu Jeon, Hyung Jin Shim, Jin Young Cho, Bon Seung Koo, “McCARD Depletion and Uncertainty Propagation Analysis,” Proceedings of the Reactor Physics Asia 2017 (RPHA17), Chengdu, China, Aug. 24-25, (2017).

C-9 Ho Jin Park, Hyun Chul Lee, “Application of Higher Order Fission Matrix for Real Variance Analysis in McCARD Monte Carlo Eigenvalue Calculation,” M&C 2017 - International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, April 16-20, (2017).

C-10 Ho Jin Park, Kyung Hoon Lee, Chung Chan Lee, and Jin Young Cho, “Estimation of Axial Peaking Factor Uncertainty by Fuel Fabrication Error using Multiple Correlation Sampling,” Proceedings of the Reactor Physics Asia 2015 (RPHA15) Conference, Jeju, Korea, Sept. 17-18, (2015).

C-11 Ho Jin Park, Hyun Chul Lee, Hyung Jin Shim, Jin Young Cho, and Chang Hyo Kim, “Real Variance Estimation of BEAVRS Benchmark in McCARD Monte Carlo Eigenvalue Calculations," ANS MC2015 - Joint International Conference Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method • Nashville, TN • April 19-23, (2015).

C-12 Ho Jin Park, Jin Young Cho, and Jae Seung Song, and Hyung Jin Shim, “Monte Carlo Perturbation Method for Geometrical Uncertainty Analysis Using McCARD," PHYSOR2014, The Westin Miyako, Kyoto, Japan, September 28 – October 3, (2014).

C-13 Ho Jin Park, Dong Hyuk Lee, Hyung Jin Shim, Jin Young Cho, and Jae Seung Song, “Uncertainty Propagation Analysis for Yonggwang Nuclear Unit 4 by McCARD/MASTER Core Analysis System," ICAPP 2013, Jeju, Korea, April 14-18, (2013).

C-14 Ho Jin Park, Hyung Jin Shim, and Chang Hyo Kim, “Uncertainty Quantification of Few Group Diffusion Theory Constants Generated by the B1 Theory-Augmented MC method, " PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education, Knoxville, Tennessee, USA, April 15-20, (2012).

C-15 Ho Jin Park, Hyung Jin Shim, and Han Gyu Joo, and Chang Hyo Kim, “Qualification Test of Few Group Constants Generated from an MC Method by the Two-Step Neutronics Analysis System McCARD/MASTER,” M&C 2011, Rio De Janeiro, RJ, Brazil, May 8-12, (2011).

C-16 Ho Jin Park, Han Gyu Joo, Hyung Jin Shim, and Chang Hyo Kim, “Assembly Depletion with Critical Spectrum in McCARD Monte Carlo Calculations and Comparison with HELIOS,” PHYSOR 2010 - Advances in Reactor Physics to Power the Nuclear Renaissance, Pittsburgh, Pennsylvania, USA, May 9-14, (2010). 

C-17 Ho Jin Park, Hyung Jin Shim, Han Gyu Joo, Chang Hyo Kim ,“Monte Carlo Depletion and Uncertainty Analyses for a TRU Fuel Assembly Using JENDL 3.3 Covariance,” M&C 2009,  Saratoga Springs, New York, USA, May 3-7, (2009).

C-18 Hyung Jin Shim, Ho Jin Park, Han Gyu Joo, Young Il Kim, and Chang Hyo Kim, “Uncertainty Propagation in Monte Carlo Depletion Analysis,” PHYSOR 2008 - International Conference on the Physics of Reactors, Casino-Kursaal Conference Center, Interlaken, Switzerland, September 14-19, (2008).

D. Domestic Conference (43)

D-1 Ho Jin Park, "Implementation of Burnup Interval Optimization Module Based on Monte Carlo Perturbation Technique," Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 22-23, (2025).

D-2 Jimin Hur and Ho Jin Park, "Critical Experiment and Depletion Benchmark Analyses with ENDF/B-VIII.1 Evaluated Nuclear Data Library," Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 22-23, (2025).

D-3 Jeong Woo Park, Kiyun Bang, Ho Jin Park, "AGN-201K Coarse Rod Worth Calibration by Neutron Source Multiplication Method," Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 22-23, (2025).

D-4 Young Beom Shon and Ho Jin Park, "Comparison of Thermal Hydraulic Feedback Solutions between McCARD and DeCART2D/MASTER for SMART Benchmark Problem," Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 22-23, (2025).

D-5 Chihun Kim and Ho Jin Park, "Application of Metaheuristic Algorithms in the Optimization of Multi-group Cross Section Libraries for Lattice Transport Codes," Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 22-23, (2025).

D-6 Young Beom Shon, Jeong Woo Park, Chihun Kim, Ho Jin Park, "Preliminary Analysis of Boron-Free Operation Small Modular Reactor using McCARD and DeCART2D," Transactions of the Korean Nuclear Society Autumn Meeting, Changwon, Korea, October 24-25, (2024).

D-7 Min Ju Kim and Ho Jin Park, "Validation of DeCART2D Criticality Calculations for LEU+ loaded SMR Systems," Transactions of the Korean Nuclear Society Autumn Meeting, Changwon, Korea, October 24-25, (2024).

D-8 Jeong Seok Kim and Ho Jin Park, "Sensitivity Analysis of MHTGR-350 Single Block Problem with DeCART2D/CAPP Code System," Transactions of the Korean Nuclear Society Autumn Meeting, Changwon, Korea, October 24-25, (2024).

D-9 Kiyun Bang and Ho Jin Park, "Development of Reactivity Analysis Module for Virtual Reality Reactor Experiment Laboratory of AGN-201K Educational and Research Reactor," Transactions of the Korean Nuclear Society Autumn Meeting, Changwon, Korea, October 24-25, (2024).

D-10 Jimin Hur and Ho Jin Park, "Stochastic Sampling Based DeCART2D/MASTER Uncertainty Quantification Analysis with ENDF/B-VII.1 Covariance Data for Hanbit Unit 3 Cycles 1," Transactions of the Korean Nuclear Society Autumn Meeting, Changwon, Korea, October 24-25, (2024).

D-11 Ho Jin Park and Jeongwoo Park, " Approach to Criticality and Control Rod Worth Calculations by McCARD with Improved AGN-201K Educational and Research Reactor Benchmark Model," Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 9-10, (2024).

D-12 Seung-Ah Yang and Ho Jin Park, " Online Kalman Filter Fission Source Convergence Diagnosis in Monte Carlo Eigenvalue Calculation,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 9-10, (2024).

D-13 Jeongwoo Park and Ho Jin Park, " Core Follow Calculations for Hanbit Unit 3 Cycles 1 and 2 using the McCARD/MASTER code system,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 9-10, (2024).

D-14 Chihun Kim, Seungsu Yuk, and Ho Jin Park, " Preliminary Benchmarking of DeCART2D/MASTER Two-Step Core Design System for APR-1400 Benchmark using Improved Cross Section Library,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 9-10, (2024).

D-15 Seung-Ah Yang and Ho Jin Park, "Monte Carlo Fission Source Convergence Diagnosis by Skewness and Kurtosis Estimation Method for Various Benchmark Problems," Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 18-19, (2023).

D-16 Ho Jin Park, "Sensitivity and Uncertainty Analyses for Similarity Coefficient Generation in Monte Carlo Calculations," Transactions of the Korean Nuclear Society Autumn Meeting, Changwon, Korea, October 20-21, (2022).

D-17 Seung-Ah Yang and Ho Jin Park, "Evaluation of Pin Power Distribution Uncertainty for KRITZ-2:13 and KRITZ-2:19 critical experiment benchmarks by McCARD," Transactions of the Korean Nuclear Society Autumn Meeting, Changwon, Korea, October 20-21, (2022).

D-18 Ho Jin Park, Mohammad Alosaimi, Sung Hoon Choi, Heejeong Jeong, Seung-su Yuk, and Yonghee Choi, "Bias Evaluations in McCARD Criticality Analysis for Low-enriched Uranium Thermal Critical Experiment Benchmarks," Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 19-20, (2022).

D-19 Ho Jin Park and Jin Young Cho, “Nuclear Data Uncertainty Estimation in DeCART Calculations by Stochastic Sampling Method,” Transactions of the Korean Nuclear Society Virtual Spring Meeting, May 13-14, (2021).

D-20 Ho Jin Park, “Validation of Uncertainty Propagation Formulation in Monte Carlo Burnup Analysis by Direct Stochastic Sampling Method,” Transactions of the Korean Nuclear Society Virtual Autumn Meeting, October 22-23, (2020).

D-21 Ho Jin Park, Tae Young Han, and Jin Young Cho, “A Implementation of Cross Section Random Sampling Code System for Direct Sampling Method in Continuous Energy Monte Carlo Calculations,” Transactions of the Korean Nuclear Society Virtual Spring Meeting, July 9-10, (2020).

D-22 Ho Jin Park and Jin Young Cho, Skewness and Kurtosis Estimation Method for Fission Source Convergence Diagnosis in Monte Carlo Eigenvalue Calculations,” Transactions of the Korean Nuclear Society Virtual Spring Meeting, July 9-10, (2020).

D-23 Ho Jin Park and Jin Young Cho, “A New Approach for Real Variance Estimation using Local Tally Correlation Between Neighboring Cells,” Transactions of the Korean Nuclear Society Spring Mtg., Jeju, Korea, May 23-24, (2019).

D-24 Ho Jin Park, Tae Young Han, and Jin Young Cho, “MIG 1.5 Code for Random Sampling of Multiple Correlated Variables,” Transactions of the Korean Nuclear Society Autumn Mtg., Yeosu, Korea, October 25-26, (2018).

D-25 Ho Jin Park, Haelee Hyun, and Jin Young Cho, “Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 McCARD Results for Criticality Benchmark and TMI-1 Pin Problems” Transactions of the Korean Nuclear Society Spring Mtg., Jeju, Korea, May 17-18, (2018).

D-26 Ho Jin Park and Jin Young Cho, “Adaptation of Critical Buckling by Monte Carlo Method to DeCART2D Calculations for TCA Critical Facility,” Transactions of the Korean Nuclear Society Spring Mtg., Jeju, Korea, May 17-18, (2018).

D-27 Ho Jin Park and Jin Young Cho, “VERA Pin and Fuel Assembly Depletion Benchmark Calculations by McCARD and DeCART” Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, October 27-28, (2016).

D-28 Ho Jin Park, Kang Seog Kim, Ser Gi Hong, and Jin Young Cho, “Multi-Group Library Generation with Explicit Resonance Interference Using Continuous Energy Monte Carlo Calculation” KNS 2016 Spring Mtg., Jeju, Korea, May 12-13, (2016).

D-29 Ho Jin Park and Hyung Jin Shim, “Application of Higher Order Fission Matrix for Real Variance Estimation in McCARD Monte Carlo Eigenvalue Calculation” KNS 2015 Spring Mtg., Jeju, Korea, May 7-8, (2015).

D-30 Ho Jin Park, Hyun Chul Lee, Hyung Jin Shim, and Chang Hyo Kim, “Real Variance Estimation of BEAVRS whole core benchmark in Monte Carlo Eigenvalue Calculations” KNS 2014 Autumn Mtg., Pyeongchang, Korea, October 30-31, (2014).

D-31 Ho Jin Park, Jin Young Cho, Hyung Jin Shim, “Sensitivity and Uncertainty Analysis for UAM Pin-Cell Benchmark by McCARD” KNS 2014 Spring Mtg., Jeju, Korea, May 29-30, (2014).

D-32 Ho Jin Park, Hyung Jin Shim, Chang Je Park, and Byung Chul Lee, “Monte Carlo Perturbation Method for Geometrical Uncertainty Analysis” KNS 2013 Spring Mtg., Gwangju, Korea, May 30-31, (2013).

D-33 Ho Jin Park and Hyung Jin Shim, “Monte Carlo Few Group Constants Generation Considering the Free-Monatomic-Gas Models,” KNS 2012 Mtg., Gyeongju, Korea, October 25-26, (2012).

D-34 Ho Jin Park and Hyung Jin Shim, “Generation of Transport Lattice code KARMA Library with Doppler-Broadening Rejection Correction Method,” KNS 2012 Mtg., Gyeongju, Korea, October 25-26, (2012).

D-35 Ho Jin Park, Jin Young Cho, Jae Seung Song, Hyung Jin Shim, “Preliminary Study for Few Group Constants Generation by a Whole Core Monte Carlo Calculation,” KNS 2012 Spring Mtg., JeJu, Korea, May 17-18, (2012).

D-36 Ho Jin Park, Hyung Jin Shim, Do Heon Kim, Choong Sup Gil, and Chang Hyo Kim, “Validation of Adjoint Sensitivity and Uncertainty Analysis Capability of McCARD,” KNS 2011 Autumn Mtg., Gyeongju, Korea, October 27-28, (2011).

D-37 Ho Jin Park, Hyung Jin Shim, Han Gyu Joo, and C. H. Kim, “Monte Carlo Nuclear Data Uncertainty Analysis for VENUS-1 criticality,” KNS 2011 Spring Mtg., TaeBaek, Korea, May 26-27, (2011).

D-38 Ho Jin Park, Hyung Jin Shim, Han Gyu Joo, and C. H. Kim, “Qualification of McCARD/MASTER Code System for Yonggwang Unit 4,” KNS 2011 Spring Mtg., TaeBaek, Korea, May 26-27, (2011)

D-39 Ho Jin Park, Han Gyu Joo, Hyung Jin Shim, and C. H. Kim, “Monte Carlo Depletion with Critical Spectrum for Assembly Group Constants Generation,” KNS Spring Mtg. (2010).

D-40 Ho Jin Park, Min Su Kwak, Jaewoon Yoo, Han Gyu Joo, and C. H. Kim, “Analysis of Metallic Uranium Fueled BFS Experiments using McCARD,” KNS Spring Mtg. (2009).

D-41 Ho Jin Park, Min Su Kwak, Han Gyu Joo, Chang Hyo Kim, “Generation and Verification of ENDF/B-VII.0 Cross section Libraries for Monte Carlo Calculations,” KNS Autumn Mtg. (2007).

D-42 Ho Jin Park, Hyung Jin Shim, and Chang Hyo Kim, “Monte Carlo Thermal Hydraulic Feedback Calculation for KALIMER Analysis,” KNS Autumn Mtg. (2006).

D-43 Ho Jin Park and Chang Hyo Kim, “Dependence of Monte Carlo Prediction on Evaluated Nuclear Data Library in Continuous Energy Criticality Calculation,” KNS Autumn Mtg. (2005).

E. INVITED TALKS

E-1. “Assessment of Evaluated Nuclear Data Libraries for Next Generation Reactor Design,”KNS (Korea Nuclear Society) Workshop, October 23, (2024).

E-2. “Monte Carlo Depletion Analysis using McCARD code – Basic and Practice,” Kyung Hee University, November 8, (2018).

E-3. “Neutron’s Life Cycle Simulation by Monte Carlo Method - Basic,” Mini-course for Radiation and Nuclear Core Design Analysis, Pusan National University, July 12, (2017).

E-4. “Present Status of the Use of McCARD Monte Carlo Code in KAERI,” Monte Carlo Code Expert Group Workshop in KAERI, May 25, (2017).

E-5. “Monte Carlo Method/Monte Carlo Eigenvalue Problem and Practice,” Kyung Hee University, June 3-17, (2016). 

E-6. “Uncertainty Propagation in Monte Carlo Depletion Analysis for a TRU Fuel Assembly,” UNIST (Ulsan National Institute of Science and Technology), May 17, (2016).

E-7. “Bias of Sample Variance and Real Variance Estimation in Monte Carlo Eigenvalue Calculations: Part II – Application for BEAVRS whole core problem,” Workshop on Advanced Monte Carlo Method, Kyoto University Research Reactor Institute, July 21-22, (2015).

E-8. “Generation of Assembly-Homogenized Few Group Constants Generation and Estimation of Their Uncertainty by Monte Carlo Method,” KNS (Korea Nuclear Society) Workshop, May 30, (2013).

E-9. “Generation of Assembly-Homogenized Few Group Constants Generation by Monte Carlo Method,” UNIST (Ulsan National Institute of Science and Technology), Feb. 7-8, (2011).

F. TECHNICAL REPORTS

F-1. Ho Jin Park et al., “McCARD Benchmark Calculation,” SNUMCL/TR001/2011(02) (2011).

F-2. Ho Jin Park et al., “Multi-group Cross Section Generation for Deep-Burn LWR,” KAERI/CM-1448/2011 (2011).

F-3. Ho Jin Park et al., “A Continuous Energy Monte Carlo Analyses for Yalina and IPEN/MB-01 Subcritical System by McCARD,” IAEA Coordinated Research Projects (CRPs) - Analytical and Experimental Analysis of Accelerator Driven Systems, (2009).

PROFESSIONAL ACTIVITIES

Korean Nuclear Society: Member

Annals of Nuclear Energy: Reviewer

Nuclear Engineering and Technology: Editor (2024.Sep~2026.Aug), Reviewer

Journal of Nuclear Science and Technology: Reviewer

Progress in Nuclear Energy: Reviewer

Energies: Reviewer