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Han Gyu Joo

Seoul National University · Engineering

About the Lab

Professor Han Gyu Joo's research lab specializes in advanced reactor physics and computational nuclear engineering, focusing on high-fidelity whole-core nuclear core analysis using deterministic and stochastic methods. The lab develops innovative transport and diffusion methodologies, including the DeCART and nTRACER codes, for accurate and efficient simulation of light water reactors under various operating conditions. Key research directions include advanced acceleration techniques such as CMFD and preconditioned Krylov solvers, resonance treatment with spectral superhomogenization, and dynamic feedback modeling for improved core performance prediction.

reactor core analysiswhole-core transport calculationcoarse mesh finite differenceresonance treatmentparallel computing in nuclear engineering

Research Overview

Papers
147
Total Citations
1,914
Papers (5y)
33
Primary Field
Engineering

Research Output Trend

Figures are computed from collected data and may differ slightly.

Publications per year (5y)
33total
2021
2022
2023
2024
2025
Citations per year (5y)
165total
20212022202320242025

Selected Papers

15
1
Article|171 citations·2013
Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers
Yeon Sang Jung, Cheon-Bo Shim, Chang Hyun Lim, Han Gyu Joo
SJR Q1Annals of Nuclear Energy
Aerospace EngineeringEngineering
2
Article|152 citations·2004
Methods and performance of a three-dimensional whole-core transport code DeCART
Han Gyu Joo, Jin Young Cho, Kang Seog Kim, Chung Chan Lee, Sung Quun Zee
Seoul National University Open Repository (Seoul National University)OA

DeCART is a three-dimensional whole-core transport code capable of performing direct core calculations at power generating conditions without involving a priori homogenized few-group constant generation. In this paper, the methods of DeCART, which are characterized by the planar method of characteristics (MOC) solutions, the cell based coarse mesh finite difference (CMFD) formulation, the subgroup method for resonance treatment and subpin level thermal feedback, are presented as a whole. The per

Aerospace EngineeringEngineering
3
Article|74 citations·2015
Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code
Min Sang Ryu, Yeon Sang Jung, Hyun Ho Cho, Han Gyu Joo
SJR Q2Journal of Nuclear Science and TechnologyOA

The BEAVRS (Benchmark for Evaluation and Validation of Reactor Simulation) benchmark is solved by the nTRACER direct whole core calculation code to assess its accuracy and to examine the solution dependence on modeling parameters.A sophisticated nTRACER core model representing the BEAVRS core is prepared after a series of sensitivity study to ensure solution accuracy.The resulting solutions for several hot-zero-power (HZP) states are compared first with the corresponding Monte Carlo solutions, w

Aerospace EngineeringEngineering
4
Article|44 citations·2006
Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code
Jin Young Cho, Han Gyu Joo
SJR Q1Progress in Nuclear Energy
Electrical and Electronic EngineeringEngineering
5
Article|44 citations·2009
Subgroup weight generation based on shielded pin-cell cross section conservation
Han Gyu Joo, Gwan Young Kim, Leonid Pogosbekyan
SJR Q1Annals of Nuclear Energy
Aerospace EngineeringEngineering
6
Article|44 citations·2013
Coarse mesh finite difference formulation for accelerated Monte Carlo eigenvalue calculation
Min Jae Lee, Han Gyu Joo, Deokjung Lee, Kord Smith
SJR Q1Annals of Nuclear Energy
Aerospace EngineeringEngineering
7
Article|39 citations·2002
DYNAMIC IMPLEMENTATION OF THE EQUIVALENCE THEORY IN THE HETEROGENEOUS WHOLE CORE TRANSPORT CALCULATION
Han Gyu Joo, Jin Young Cho, Ha Yong Kim, Sung Quun Zee, Moon Hee Chang
Seoul National University Open Repository (Seoul National University)OA

The coarse mesh finite difference (CMFD) formulation is applied to the heterogeneous whole transport calculation as a means of efficient acceleration as well as simplified representation. A pin cell is chosen as the base coarse mesh which is much coarser than the intra-cell flat source regions. The CMFD formulation enables dynamic homogenization of the cells during the iterative solution process such that the heterogeneous transport solution can be preserved. Dynamic group condensation is also p

Aerospace EngineeringEngineering
8
Article|35 citations·2021
Optimization of neutron tracking algorithms for GPU-based continuous energy Monte Carlo calculation
Namjae Choi, Kyung Min Kim, Han Gyu Joo
SJR Q1Annals of Nuclear Energy
Aerospace EngineeringEngineering
9
Article|32 citations·1996
An Incomplete Domain Decomposition Preconditioning Method for Nonlinear Nodal Kinetics Calculations
Han Gyu Joo, Thomas Downar
SJR Q2Nuclear Science and Engineering

Methods are proposed for the efficient parallel solution of nonlinear nodal kinetics equations. Because the two-node calculation in the nonlinear nodal method is naturally parallelizable, the majority of the effort is devoted to the development of parallel methods for solving the coarse-mesh finite difference (CMFD) problem. A preconditioned Krylov subspace method (biconjugate gradient stabilized) is chosen as the iterative algorithm for the CMFD problem, and an efficient parallel preconditionin

Computational Theory and MathematicsComputer Science
10
Article|31 citations·2008
Multigroup pin power reconstruction with two-dimensional source expansion and corner flux discontinuity
Han Gyu Joo, Joo Il Yoon, S. G. Baek
SJR Q1Annals of Nuclear Energy
Aerospace EngineeringEngineering
11
Article|26 citations·2017
Practical resolution of angle dependency of multigroup resonance cross sections using parametrized spectral superhomogenization factors
Hansol Park, Han Gyu Joo
SJR Q2Nuclear Engineering and TechnologyOA

Based on the observation that ignoring the angle dependency of multigroup resonance cross sections within a fuel pellet would result in nontrivial underestimation of the spatial self-shielding of flux, a parametrized spectral superhomogenization (SPH) factor library (PSSL) method is developed as a practical means of resolving the problem. Region-wise spectral SPH factors are calculated by the normal and transport corrected SPH iterations after ultrafine group slowing down calculations over vario

Aerospace EngineeringEngineering
12
Article|21 citations·2014
COARSE MESH FINITE DIFFERENCE ACCELERATION OF DISCRETE ORDINATE NEUTRON TRANSPORT CALCULATION EMPLOYING DISCONTINUOUS FINITE ELEMENT METHOD
Dong Wook Lee, Han Gyu Joo
SJR Q2Nuclear Engineering and TechnologyOA

The coarse mesh finite difference (CMFD) method is applied to the discontinuous finite element method based discrete ordinate calculation for source convergence acceleration. The three-dimensional (3-D) DFEM-Sn code FEDONA is developed for general geometry applications as a framework for the CMFD implementation. Detailed methods for applying the CMFD acceleration are established, such as the method to acquire the coarse mesh flux and current by combining unstructured tetrahedron elements to rect

Computational MechanicsEngineering
13
Article|19 citations·2020
Investigation of Anderson acceleration in neutronics-thermal hydraulics coupled direct whole core calculation
Alberto Facchini, Jaejin Lee, Han Gyu Joo
SJR Q1Annals of Nuclear Energy
Aerospace EngineeringEngineering
14
Article|19 citations·2020
Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation
Namjae Choi, Han Gyu Joo
SJR Q2Nuclear Engineering and TechnologyOA

A domain decomposition (DD) scheme for GPU-based Monte Carlo (MC) calculation which is essential for whole-core depletion is introduced within the framework of the modified history-based tracking algorithm. Since GPU-offloaded MC calculations suffer from limited memory capacity, employing DDMC is inevitable for the simulation of depleted cores which require large storage to save hundreds of newly generated isotopes. First, an automated domain decomposition algorithm named wheel clustering is dev

Aerospace EngineeringEngineering
15
Article|19 citations·2018
A reduced-basis element method for pin-by-pin reactor core calculations in diffusion andSP3approximations
Alexey Cherezov, Richard Sanchez, Han Gyu Joo
SJR Q1Annals of Nuclear Energy
Statistical and Nonlinear PhysicsPhysics and Astronomy

Research Areas

Aerospace EngineeringElectrical and Electronic EngineeringMaterials ChemistryComputational MechanicsNumerical AnalysisBiomedical Engineering

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