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Showing results 1 to 31 of 31

Issue Date	Title / Author(s) / Citation	File
1998-09	Stabilization techniques for the nonlinear analytic nodal method Joo, Han Gyu; Jiang, Guibing; Downar, Thomas J. Nucl. Sci. Eng., 130, 47 (1998)	view file
1999-05	LMR core temperature calculation based on implicit formulation of the ENERGY model and a Krylov subspace method Yang, Won Sik; Joo, Han Gyu Ann. Nucl. Eng. 26, 629	DOI
2001-08	A preconditioned Krylov method for solution of the multi-dimensional, two fluid hydrodynamics equations Downar, Thomas J.; Joo, Han Gyu Ann. Nucl. Eng. 28, 1251	DOI
2002-06	Cell based CMFD formulation for acceleration of whole-core method of characteristics calculation Cho, Jin Young; Joo, Han Gyu; Kim, Kang Seog J. Korean Nuc. Soc.. 34, 250 (2002).	view file
2002-10	Dynamic implementation of the equivalence theory in the heterogeneous whole core transport calculation Joo, Han Gyu; Cho, Jin Young PHYSOR 2002 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Seoul, Korea, October 7-10, 2002	view file
2003-05	Analysis of the OECD main steam line break benchmark problem using the refined core thermal-hydraulic nodalization feature of the MARS/MASTER code Joo, Han Gyu; Jeong, Jae Jun; Cho, Byung Oh; Lee, Won Jae; Zee, Sung Quun Nucl. Technol., 142, 166 (2003)	view file link
2004-04	Methods and performance of a three-dimensional whole-core transport code DeCART Joo, Han Gyu; Cho, Jin Young; Kim, Kang Seog; Lee, Chung Chan; Zee, Sung Quun PHYSOR 2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Illinois, April 25-29, 2004	view file
2006-07	Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code Cho, Jin Young; Joo, Han Gyu Prog. Nucl. Energy 48, 456	DOI
2007-03	High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor Weber, David P.; Joo, Han Gyu Nucl. Sci. Eng., 155, 395 (2007)	view file
2007-08	Derivation of Analytic Solution and MOC Calculation Procedure for Double Heterogeneity Treatment Joo, Han Gyu; Park, Tong Kyu	view file
2007-09	Implementation of the Sanchez-Pomraning Double Heterogeneity Treatment Method in DeCART Pogosbekyan, Leonid; Joo, Han Gyu	view file
2008-07	Two-level coarse mesh finite difference formulation with multigroup source expansion nodal kernels Yoon, Joo Il; Joo, Han Gyu J. Nucl. Sci. Technol., 45, 668 (2008)	view file DOI
2008-11	Multi-group unified nodal method with two-group coarse-mesh finite difference formulation Han, Tae Young; Joo, Han Gyu; Lee, Hyun Chul; Kim, Chang Hyo Ann. Nucl. Eng. 35, 1975	DOI
2009-01	Multigroup pin power reconstruction with two-dimensional source expansion and corner flux discontinuity Joo, Han Gyu; Yoon, Joo Il; Baek, Seung Gyou Ann. Nucl. Eng. 36, 85	DOI
2009-06	Multiobjective loading pattern optimization by simulated annealing employing discontinuous penalty function and screening technique Park, Tong Kyu; Joo, Han Gyu; Kim, Chang Hyo; Lee, Hyun Chul Nucl. Sci. Eng., 162, 134 (2009)	view file
2009-07	Subgroup weight generation based on shielded pin-cell cross section conservation Joo, Han Gyu; Kim, Gwan Young; Pogosbekyan, Leonid Ann. Nucl. Eng. 36, 859	DOI
2015-12	Pointwise cross-section-based on-the-fly resonance interference treatment with intermediate resonance approximation Bacha, Meer; Joo, Han Gyu Nuclear Engineering and Technology, Vol.47 No.7, pp.791-803	DOI
2016	Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions Hursin, Mathieu; Downar, Thomas J.; Yoon, Joo Il; Joo, Han Gyu Annals of Nuclear Energy, vol.87, pp. 356-365
2016-01	Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions Hursin, Mathieu; Downar, Thomas J.; Yoon, Joo Il; Joo, Han Gyu Annals of Nuclear Energy, Vol.87, pp.356-365	DOI
2016-10	Temperature dependent subgroup formulation with number density adjustment for direct whole core power reactor calculation Jung, Yeon Sang; Lim, Chang Hyun; Joo, Han Gyu Annals of Nuclear Energy, Vol.96, pp.249-263	DOI
2020-08	Stability enhancement of planar transport solution based whole-core calculation employing augmented axial method of characteristics Choi, Namjae; Joo, Han Gyu Annals of Nuclear Energy, Vol.143, p. 107440	DOI
2021-03	Practical acceleration of direct whole-core calculation employing graphics processing units Choi, Namjae; Kang, Junsu; Lee, Han Gyu; Joo, Han Gyu Progress in Nuclear Energy, Vol.133, p. 103631	DOI
2021-04	Investigation of Anderson acceleration in neutronics-thermal hydraulics coupled direct whole core calculation Facchini, Alberto; Lee, Jaejin; Joo, Han Gyu Annals of Nuclear Energy, Vol.153, p. 108042	DOI
2021-05	Analysis of C5G7-TD benchmark with a multi-group pin homogenized SP3 code SPHINCS Cho, Hyun Ho; Kang, Junsu; Yoon, Joo Il; Joo, Han Gyu Nuclear Engineering and Technology, Vol.53 No.5, pp.1403-1415	DOI
2021-09	Direct whole core modeling and simulation of the SPERT III E-Core experiments by nTRACER Kang, Junsu; Ryu, Min; Jae, Seungug; Kim, Hyeongseog; Joo, Han Gyu Progress in Nuclear Energy, Vol.139, p. 103824	DOI
2021-09	Relative Speed Tabulation Method for Efficient Treatment of Resonance Scattering in GPU-Based Monte Carlo Neutron Transport Calculation Choi, Namjae; Joo, Han Gyu Nuclear Science and Engineering, Vol.195 No.9, pp.954-964	DOI
2021-11	High performance 3D pin-by-pin neutron diffusion calculation based on 2D/1D decoupling method for accurate pin power estimation Yoon, Jooil; Lee, Hyun Chul; Joo, Han Gyu; Kim, Hyeong Seog Nuclear Engineering and Technology, Vol.53 No.11, pp.3543-3562	DOI
2021-11	Optimization of neutron tracking algorithms for GPU-based continuous energy Monte Carlo calculation Choi, Namjae; Kim, Kyung Min; Joo, Han Gyu Annals of Nuclear Energy, Vol.162, p. 108508	DOI
2021-12	Thorough analyses and resolution of various errors in pin-homogenized multigroup core calculation Hong, Hyunsik; Joo, Han Gyu Annals of Nuclear Energy, Vol.163, p. 108502	DOI
2022-02	Convergence analysis of fixed-point iteration with Anderson Acceleration on a simplified neutronics/thermal-hydraulics system Lee, Jaejin; Joo, Han Gyu Nuclear Engineering and Technology, Vol.54 No.2, pp.532-545	DOI
2022-12	Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data Papadionysiou, Marianna; Kim, Seongchan; Hursin, Mathieu; Vasiliev, Alexander; Ferroukhi, Hakim; Pautz, Andreas; Joo, Han Gyu Annals of Nuclear Energy, Vol.178, p. 109385	DOI