MEMBERS

• Joo Han-gyu
• Department of Nuclear Engineering Seoul National University
• 599 Gwanak-ro, Seoul, 151-744, Korea
• Tel : +82-2-880-9241
• Fax : +82-2-889-2688
• Email : joohan@snu.ac.kr

Education

• Purdue University, U.S.A.
  
  • Ph.D., Department of Nuclear Engineering (1996)
• Seoul National University, Korea
  
  • M.S., Department of Nuclear Engineering (1986)
• Seoul National University, Korea
  
  • B.S., Department of Nuclear Engineering (1984)

Career

• Seoul National University, Department of Nuclear Engineering
  
  • 2009.10 – Present Professor
  • 2004.08 – 2009.09 Associate Professor
• Korea Atomic Energy Research Institute(KAERI), Reactor Engineering Department
  
  • 2002.09 – 2004.08 Principal Researcher
  • 1998.06 – 2002.08 Senior Researcher
  • 1997.08 – 1998.06 Post Doctoral Researcher
• Purdue University, Department of Nuclear Engineering
  
  • 1996.05 – 1997.07 Post Doctoral Research Associate
  • 1993.01 – 1996.05 Research Assistant
• Korea Atomic Energy Research Institute(KAERI), Initial Core Design Department
  
  • 1990.09 – 1992.12 Senior Researcher
  • 1986.02 – 1990.08 Researcher

Research Interests and Achievements

Professional Societies

• Korean Nuclear Society: Lifetime member since 2004
• American Nuclear Society: fellow of ANS since 2015

Honors and Awards

• National Overseas Study Scholarship: Korean Government, 1993-1996
• ANS Best Paper Award: ANS Reactor Physics Division, Winter Meeting, 1995
• KNS Best Paper Award: KNS Fall Meeting, 1995
• KNS Best Paper Award: KNS Spring Meeting, 2000
• Doosan Nuclear Technology Award: Korean Nuclear Society, 2010

Archival Journal Publications

• Vasiliev, A., Canepa, S., Ferroukhi, H., Boyarinov, V. F., Fomichenko, P. A., Joo, H. G., & Ryu, M. (2019). Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark. Annals of Nuclear Energy, 134, 235-243.
• Lee, J., Facchini, A., & Joo, H. G. (2019). Development of a drift-flux model based core thermal-hydraulics code for efficient high-fidelity multiphysics calculation. Nuclear Engineering and Technology, 51(6), 1487-1503.
• Park, H., & Joo, H. G. (2019). Effective subgroup method employing macro level grid optimization for LWR applications. Annals of Nuclear Energy, 129, 461-471.
• Cherezov, A., Sanchez, R., & Joo, H. G. (2018). A reduced-basis element method for pin-by-pin reactor core calculations in diffusion and SP3 approximations. Annals of Nuclear Energy, 116, 195-209.
• Ban, Y. S., Masiello, E., Lenain, R., Joo, H. G., & Sanchez, R. (2018). Code-to-code comparisons on spatial solution capabilities and performances between nTRACER and the standalone IDT solver of APOLLO3®. Annals of Nuclear Energy, 115, 573-594.
• Lim, C., Joo, H. G., & Yang, W. S. (2018). Development of a fast reactor multigroup cross section generation code EXUS-F capable of direct processing of evaluated nuclear data files. Nuclear Engineering and Technology, 50(3), 340-355.
• Choi, N., Kang, J., & Joo, H. G. (2018, January). Massively parallel method of characteristics neutron transport calculation with anisotropic scattering treatment on GPUs. In Proceedings of the International Conference on High Performance Computing in Asia-Pacific Region (pp. 148-158).
• Park, H., & Joo, H. G. (2018). The Impact of Hydrogen Asymptotic Scattering Approximations on Thermal Reactor Analysis in Deterministic Multi-Group Approach. Transactions, 119(1), 1120-1123.
• Park, H., & Joo, H. G. (2017). Practical resolution of angle dependency of multigroup resonance cross sections using parametrized spectral superhomogenization factors. Nuclear Engineering and Technology, 49(6), 1287-1300.
• Sanchez, R., Tomatis, D., Zmijarevic, I., & Joo, H. G. (2017). Analysis of alpha modes in multigroup diffusion. Nuclear Engineering and Technology, 49(6), 1259-1268.
• Lim, C., Joo, H. G., & Yang, W. S. (2017). Application of Probability Table Method for Unresolved Resonance Self-Shielding in Deterministic Codes. Transactions, 117(1), 1278-1281.
• Y. S. Jung, C. H. Lim, H. G. Joo, “Temperature dependent subgroup formulation with number density adjustment for direct whole core power reactor calculation,” Annals of Nuclear Energy, 96, 249-263 (2016).
• M. Hursin, T. J. Downar, J. I. Yoon, H. G. Joo, “Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions,” Annals of Nuclear Energy, 87, 356-365 (2016).
• M. Bacha, H. G. Joo, “Pointwise cross-section-based on-the-fly resonance interference treatment with intermediate resonance approximation,” Nuclear Engineering and Technology, 47, 791-803 (2015).
• B. W. Park, H. G. Joo, “Improved stiffness confinement method within the coarse mesh finite difference framework for efficient spatial kinetics calculation,” Annals of Nuclear Energy, 76, 200-208 (2015).
• M. Ryu, Y. S. Jung, H. H. Cho, H. G. Joo, “Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code ,” Journal of Nuclear Science and Technology, 52, 961-969 (2015).
• S. J. Noh, S. K. Lee, H. S. Kim, S. H. Yun, H. G. Joo, “Deuterium permeation and isotope effects in nickel in an elevated temperature range of 450-850 °c,” International Journal of Hydrogen Energy, 39, 12789-12794 (2014).
• T. K. Park, H. G. Joo, C. H. Kim, “Multicycle fuel loading pattern optimization by multiobjective simulated annealing employing adaptively constrained discontinuous penalty function,” Nuclear Science and Engineering, 176, 226-239 (2014).
• D. W. Lee, H. G. Joo, “Coarse mesh finite difference acceleration of discrete ordinate neutron transport calculation employing discontinuous finite element method,” Nuclear Engineering and Technology, 46, 783-796 (2014).
• M. J. Lee, H. G. Joo, D. Lee, K. Smith, “Coarse mesh finite difference formulation for accelerated Monte Carlo eigenvalue calculation,” Annals of Nuclear Energy, 65, 101-113 (2014).
• S. K. Lee, S. H. Yun, H. G. Joo, S. J. Noh, “Deuterium transport and isotope effects in type 316L stainless steel at high temperatures for nuclear fusion and nuclear hydrogen technology applications,” Current Applied Physics, 14, 1385-1388 (2014).
• Y. H. Choi, H. G. Joo, “Multiscale simulation of neutron induced damage in tritium breeding blankets with different spectral shifters,” Fusion Engineering and Design, 88, 2471-2474 (2013).
• H. J. Park, H. G. Joo, H. J. Shim, C. H. Kim, “Uncertainty quantification of few-group diffusion theory constants generated by the Bi theory-augmented Monte Carlo method,” Nuclear Science and Engineering, 175, 28-43 (2013).
• Y. S. Jung, C. B. Shim, C. H. Lim, H. G. Joo, “Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers,” Annals of Nuclear Energy, 62, 357-374 (2013).
• E. H. Ryu, H. G. Joo, “Finite element method solution of the simplified P3 equations for general geometry applications,” Annals of Nuclear Energy, 56, 194-207 (2013).
• H. J. Park, H. J. Shim, H. G. Joo, C. H. Ki, “Generation of few-group diffusion theory constants by Monte Carlo code McCARD,” Nuclear Science and Engineering, 172, 66-77 (2012).
• Y. H. Choi, H. G. Joo, “Analysis of neutron spectrum effects on primary damage in tritium breeding blankets,” Journal of Nuclear Materials, 426, 16-25 (2012).
• C. B. Shim, Y. S. Jung, J. I. Yoon, H. G. Joo, “Application of backward differentiation formula to spatial reactor kinetics calculation with adaptive time step control,” Nuclear Engineering and Technology, 43, 531-546 (2011).
• B. G. Hong, Y. S. Hwang, J. S. Kang, D. W. Lee, H. G. Joo, M. Ono , “Conceptual design study of a superconducting spherical tokamak reactor with a self-analysis code,” Nuclear Fusion, 51, 113013 (2011).
• H. J. Park, H. G. Joo, H. J. Shim, C. H. Kim, C. S. Gil, “Effect of cross section uncertainties on criticality benchmark problem analysis by McCARD,” Journal of the Korean Physical Society, 59, 1252-1255 (2011).
• S. Choi, J. H. Cho, M. H. Bae, J. Lim, D. Puspitarini, J. H. Jeun, H. G. Joo, I. S. Hwang, “PASCAR: Long burning small modular reactor based on natural circulation,” Nuclear Engineering and Design, 241, 1486-1499 (2011).
• Han Gyu Joo, Gwan Young Kim, Leonid Pogosbekyan, “Subgroup Weight Generation Based on Shielded Pin-Cell Cross Section Conservation,” Annals of Nuclear Energy, 36,859-868 (2009).
• Tong Kyu Park, Han Gyu Joo (Corresponding Author), Chang Hyo Kim and Hyun Chul Lee, “Multiobjective Loading Pattern Optimization by Simulated Annealing Employing Discontinuous Penalty Function and Screening Technique,” Nucl. Sci. Eng., 162, 134-147 (2009).
• Han Gyu Joo, Joo Il Yoon, and Seung Gyu Baek. “Multigroup pin power reconstruction with two-dimensional source expansion and corner flux discontinuity,”Annals of Nuclear Energy, 36, 85-97 (2009).
• Tae Young Han, Han Gyu Joo (Corresponding Author), Hyun Chul Lee and Chang Hyo Kim, “Multi-group unified nodal method with two-group coarse-mesh finite difference formulation,” Annals of Nuclear Energy, 35, 1975-1985 (2008).
• Jin Young Cho, Kang Seog Kim, Hyung Jin Shim, Jae Seung Song, Chung Chan Lee and Han Gyu Joo., “Whole core transport calculation employing hexagonal modular ray tracing and CMFD formulation,” Journal of Nuclear Science and Technology, 45, 740-751 (2008).
• Joo Il Yoon and Han Gyu Joo (Corresponding Author), “Two-Level Coarse Mesh Finite Difference Formulation with Multigroup Source Expansion Nodal Kernels,” Journal of Nuclear Science and Technology, 45, 668-682 (2008)
• Jin Young Cho, Kang-Seog Kim, Chung-Chan Lee, Sung-Quun Zee, and Han Gyu Joo, (Corresponding Author), “Axial SPN and Radial MOC Coupled Whole Core Transport Calculation,” J. Nucl. Sci. Tech., 44, 1156-1171 (2007).
• D. P. Weber, Han Gyu Joo et al. (Corresponding Author), “High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor,” Nucl. Sci. Eng., 155, 395-408 (2007).
• Jin Young Cho and Han Gyu Joo (Corresponding Author), “Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code,” Prog. Nucl. Ener., 48, 456-466 (2006).
• T. Kowzlowksy, R. M. Miller, T. J. Downar, D. A. Barber, and Han Gyu Joo, "Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark," Nuclear Technology, 142, 166 (2004).
• Han Gyu Joo, Jae Jun Jeong, Byung Oh Cho, Won Jae Lee, and Sung Quun Zee, “Analysis of the OECD Main Steam Line Break Benchmark Problem Using the Refined Core Thermal-Hydraulic Nodalization Feature of the MARS/MASTER Code,” Nuclear Technology, 146, 15 (2003).
• Jin Young Cho, Han Gyu Joo, Kang-Seog Kim, and Sung-Quun Zee., "Cell Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculation," J. of Korean Nucl. Soc., 34, 250 (2002).
• Thomas J. Downar and Han Gyu Joo, "A Preconditioned Krylov method for solution of the multi-dimensional, two-fluid hydrodynamics equations," Annals of Nuclear Energy, 28, 1251 (2001).
• Kibog Lee, Han Gyu Joo, Byung Oh Cho and Sung Quun Zee, "Current Conservation Factors for Consistent One - Dimensional Neutronics Modeling," J. of Korean Nucl. Soc, 32, 235 (2006).
• Jae Jun Jeong, Han Gyu Joo et al., "MARS / MASTER Solution to OECD Main Steam Line Break Benchmark," J. of Korean Nucl. Soc, 32, 214 (2006).
• Won Sik Yang and Han Gyu Joo, “LMR core temperature calculation based on implicit formulation of the ENERGY model and a Krylov subspace method,” Annals of Nuclear Energy , 26, 629 (1999).
• Han Gyu Joo, Guobing Jiang, and Thomas J. Downar, “Stabilization Techniques for the Nonlinear Analytic Nodal Method,” Nucl. Sci. Eng., 130, 47 (1998).
• Han Gyu Joo and Thomas J. Downar, “An Incomplete Domain Decomposition Preconditioning Method for Nonlinear Nodal Kinetics Calculation,” Nucl. Sci. Eng., 123, 403 (1996).
• Chang Hyo Kim, Jin Young Cho, and Han Gyu Joo, “Approximate Three-Dimensional Correction Factors in Two-Dimensional Reactor Calculation,” Nucl. Sci. Eng., 118, 108 (1994).