Dr. Ho Jin Park

Ho Jin Park , Ph.D.

   Korea Atomic Energy Research Institute (KAERI),
Reactor Core Design Division

Senior Researcher
   한국원자력연구원 선임연구원 박호진

EDCUATION

   2004.03 - 2011.02   Ph. D., Department of Nuclear Engineering, SNU, Korea
                                    서울대학교 에너지시스템 공학부 공학 박사

   2001.03 - 2004.02   B.S., Department of Computer Engineering, SNU, Korea
                                   서울대학교 컴퓨터공학부 학사 (복수전공)

   1999.03 - 2004.02   B.S., Department of Nuclear Engineering, SNU, Korea
                                   서울대학교 원자핵공학과 학사

EMPLOYMENT

   2011.12 -   현재        Korea Atomic Energy Research Institute, Senior Researcher
                                   한국 원자력 연구원, 선임연구원

   2013.09 - 2013.11  Oak Ridge National Laboratory, Visiting Scholar
                                   미국 오크릿지 연구소, 방문연구원

   2011.03 - 2011.12   Center for Advanced Research in Fusion Reactor Engineering, Researcher
                                    핵융합로공학 선행연구 센터, 연수연구원

   2005.09 - 2006.08   Assistant, Depaertment of Nuclear Engineering, SNU
                                   서울대학교 원자핵공학과 행정조교

DEVELOPED CODE

   McCARD        Monte Carlo Code for Neutronic Analysis of nuclear reactor system (5^th author)
                        몬테칼로 노심해석 코드

   MIG/MOCHA     Monte Carlo Few Group Constants Generation System (1^st author)
                          몬테칼로 군정수 생산 시스템 코드

HONOR AND AWARDS

Best Paper Award at KNS 2013 spring Mtg.
Verification of Sensitivity and Uncertainty Analysis Code with the GODIVA and VHTR Fuel

PUBLICATION

A. International Journal (6)

       A-1 Ho Jin Park, Hyung Jin Shim, Han Gyu Joo, and Chang Hyo Kim, “Uncertaintyquantification 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-2 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-3 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-4 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-5 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-6 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 (3)

       B-1 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-2 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-3 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 (6)

      C-1 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-2 Ho Jin Park, Hyung Jin Shim, and Chang Hyo Kim, “Uncertainty Quantification of Few Group
            Diffusion Theory Constants Generated by the B1 Theory-Augmented MCmethod, " PHYSOR
            2012 – Advances in Reactor Physics – Linking Research,Industry, and Education, Knoxville,
            Tennessee, USA, April 15-20, (2012)

      C-3 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-StepNeutronics Analysis
             System McCARD/MASTER,” M&C 2011, Rio De Janeiro, RJ,Brazil, May 8-12, (2011)

      C-4 Ho Jin Park, Han Gyu Joo, Hyung Jin Shim, and Chang Hyo Kim, “Assembly Depletion
             with Critical Spectrum in McCARD Monte Carlo Calculations andComparison with
            HELIOS,” PHYSOR 2010 - Advances in Reactor Physics to Power theNuclear Renaissance,
             Pittsburgh, Pennsylvania, USA, May 9-14, (2010)

      C-5 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-6 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 (12)

      D-1 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-2 Ho Jin Park and Hyung Jin Shim, “Monte Carlo Few Group Constants Generation Considering
the Free-Monatomic-Gas Models,” KNS 2012 Mtg., Gyeongju, Korea, October25-26, (2012)

      D-3 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-4 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-5 Ho Jin Park, Hyung Jin Shim, Do Heon Kim, Choong Sup Gil, and Chang Hyo Kim,
            “Validationof Adjoint Sensitivity and Uncertainty Analysis Capability of McCARD,”
             KNS 2011Autumn Mtg., Gyeongju, Korea, October 27-28, (2011).

       D-6 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-7 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-8 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-9 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-10 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-11 Ho Jin Park, Hyung Jin Shim, and Chang Hyo Kim, “Monte Carlo Thermal
HydraulicFeedback Calculation for KALIMER Analysis,” KNS Autumn Mtg. (2006)

      D-12 Ho Jin Park and Chang Hyo Kim, “Dependence of Monte Carlo Prediction
            on EvaluatedNuclear Data Library in Continuous Energy Criticality Calculation,”
            KNS AutumnMtg. (2005)

As a Contributor or Developer of McCARD code for Nuclear Reactor Design

    - McCARD is originally designed exclusively for neutronics analysis of multiplying media like fuel
     pins, fuel assemblies and reactors. It is a personal computer-based, continuous energy Monte
     Carlo code written in C++ language. It has depletion capability which enables users to perform
     easy-to-use depletion computations with built-in subroutines for solving the depletion
     equations. It has parallel computing capability with the help of MPI libraries, which drastically
     enhances computation speed on clustered computers.

   - Since its predecessor MCNAP was first introduced in 1999 as a MC burnup analysis tool with
     an ORIGEN2-type fuel depletion equation solver, it has evolved to a versatile MC tool that is
     capable of conducting whole-core neutronics calculations, few group diffusion theory constants
     (hereafter referred to as few group constants) generation, and uncertainty propagation calculations.

   - In the course of its evolution, a wide range of nuclear systems; such as SMART, PMR-200,
     KALIMER-600, fusion blankets, subcritical systems like HYPER, YALINA, and IPEN/MB-01 have
     been subjected to the neutronics analyses. The R&D efforts to meet both functional and
     non-functional requirements for these analyses have played crucial roles in developing McCARD
     into its current status.

   - Ho Jin Park contribute to the study of the uncertainty propagation in Monte Carlo depletion
     analysis (2006~) and of the few-group constants generation based on the Monte Carlo
     method (2009~) using McCARD.

- NET paper for McCARD code (McCARD 소개논문) [LINK]