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Showing results 1 to 46 of 46

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	전노심 수송계산에 도입된 축방향 P₃ 방정식의 이격자 준해석적 노달해법 개발 이동욱	link
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	효율적 다군 과도 노심해석을 위한 선원확장 노달법 및 봉출력 재구성법 윤주일	link
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
2010	자동화된 Krylov 부공간 확장법을 통한 행렬지수함수 기반 연소 계산능 최적화 구현 김관영	link
2010	육방형 노심해석용 삼각형 내 다항식전개 SP3 해법 개발 배무훈	link
2011-02	임의의 형상 처리를 위한 SP₃ 유한 요소 해법 개발 류은현	link
2012-02	Establishment of a Multiscale Simulation System for Prediction of Neutron Induced Radiation Hardening in Metals 최용희	link
2012-08	전노심 수송계산용 다군 핵자료 통합 생산체계 구축 임창현	view file
2013-02	전노심 SP3 계산을 위한 방향교차 일차원 선원확장 노달법 정희정	view file
2013-08	Development of Practical Numerical Nuclear Reactor for High Fidelity Core Analysis 정연상	view file
2014-02	가상흡수단면적 기반 급상승도 제한 방법을 이용한 효과적인 노심 과도계산 체계 구현 박범우	view file
2014-08	Coarse Mesh Finite Difference Acceleration of Discrete Ordinate Neutron Transport Calculation Employing Discontinuous Finite Element Method 이동욱	view file
2014-08	Acceleration of Sn Eigenvalue Calculation with Coarse Mesh Formulation Employing Angular Flux Discontinuity Factors 임채호	view file
2015-08	Development of a High-Fidelity Core Simulator Employing Advanced SP3 Nodal Methods and Backward Differentiation Formula Shim, Cheon-bo	view file
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	view file 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
2016-02	Efficient Treatment of Anisotropic Scattering in Method of Characteristics Calculations 류민	view file
2016-08	Development of a Drift-Flux Model Based Pinwise Whole Core Thermal-Hydraulics Analysis Code Aiming at Highly Parallelized Execution 이재진	view file
2018-02	Development of a Multigroup Cross Section Generator for Fast Reactor Analysis Directly Employing Evaluated Nuclear Data Files 임창현	view file
2018-02	nTRACER-RENUS 연계체계 구축과 잠수함 탑재용 원자로 노심의 핵설계 정준호	view file
2018-08	Resonance Treatment Innovations for Efficiency and Accuracy Enhancement in Direct Whole Core Calculations of Water-Cooled Power Reactors 박한솔	view file
2018-08	Development of Advanced Leakage Feedback Method for Two-step Core Analyses 반영석	view file
2019-08	Convolutional Neural Network for Prediction of Two-Dimensional Core Power Distributions in PWRs 이진영	view file link
2020	저농축 우라늄 합금 연료를 이용한 잠수함용 무붕산 경수로 노심 설계 김성배	view file link
2020	Efficient Pin Level Core Transient Simulation Employing Simplified P3 Method with Multi-Level CMFD Acceleration 황준택	view file link
2020	Pin-wise Core Analysis Method Employing Mixed One-Pin Nodal Kernels and Assembly-Level Corrected p-CMFD 백승엽	view file link
2020	Development and Optimization of a Neutronics Coupled Refined Core Thermal-Hydraulics Analysis System Capable of Massive Parallel Execution 이재진	view file link
2021-02	Development of a Pin Level Thermal/Hydraulics-Neutronics Coupled Core Simulator for High Fidelity Steady-state and Transient Analyses Facchini Alberto	view file link
2021-02	Development of Pinwise SP3 Based Fast Core Transient Analysis Methodology and the SPHINCS Code 조현호	view file link
2021-02	Development of GPU-Based Deterministic and Probabilistic Direct Whole-core Calculation Systems 최남재	view file link
2022	Enhancement of Direct Whole Core Transient Calculation Capability 강준수	view file link