Yeon Sang Jung - Concepedia

Author

Yeon Sang Jung

Also Known As

Univ. of Michigan, Ann Arbor, MI (United States) Seoul National Univ. (Korea, Republic of), Y Jung, Y. Jung, Y. S. Jung, Y.S. Jung, Yangjin Jung, Yeon Jung, Yeon Sang Jung, Yeon-Sang Jung

Publications

Citations

H-Index

Concepts

All Affiliations

Argonne National Laboratory Seoul National University Idaho National Laboratory Los Alamos National Laboratory EKOS Corporation

About

Yeon Sang Jung is an author at Argonne National Laboratory specializing in engineering, numerical analysis, and neutron transport.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	6	6	254
2	Nuclear Engineering	4	4	211
3	Natural Sciences	3	3	54
4	Computer Engineering	2	2	35
5	Electrical Engineering	1	1	11

Yeon Sang Jung

Publications

746

Citations

H-Index

Page 1

	Year	Citations
2.0 - MOOSE: Enabling massively parallel multiphysics simulation Alexander Lindsay, Derek Gaston, Cody Permann, SoftwareX	2022	227
Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers Yeon Sang Jung, Cheon-Bo Shim, Chang Hyun Lim, Annals of Nuclear Energy Numerical AnalysisEngineeringThermal HydraulicsThermal/hydraulic SolversNuclear Safety	2013	170
3.0 - MOOSE: Enabling massively parallel multiphysics simulations Guillaume Giudicelli, Alexander Lindsay, Logan Harbour, SoftwareX	2024	137
Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code Min Sang Ryu, Yeon Sang Jung, Hyun Ho Cho, Journal of Nuclear Science and Technology	2015	73
Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors Yaqi Wang, Zachary M. Prince, Hansol Park, Annals of Nuclear Energy	2024	28
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries Emily Shemon, Yinbin Miao, Shikhar Kumar, Nuclear Science and Engineering	2023	27
Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC Guangchun Zhang, Albert Hsieh, Won Sik Yang, Nuclear Science and Engineering Numerical AnalysisEngineeringComputational MechanicsNumerical ComputationNumerical Simulation	2019	24
APPLICATION OF BACKWARD DIFFERENTIATION FORMULA TO SPATIAL REACTOR KINETICS CALCULATION WITH ADAPTIVE TIME STEP CONTROL Cheon-Bo Shim, Yeon Sang Jung, Joo-Il Yoon, Nuclear Engineering and Technology Numerical AnalysisFinite Element MethodBdf MethodNumerical ComputationEngineering	2011	19
A Consistent CMFD Formulation for the Acceleration of Neutron Transport Calculations Based on the Finite Element Method Yeon Sang Jung, Won Sik Yang Nuclear Science and Engineering Numerical AnalysisEngineeringNeutron Transport CalculationsComputational MechanicsNumerical Computation	2017	19
Temperature dependent subgroup formulation with number density adjustment for direct whole core power reactor calculation Yeon Sang Jung, Chang Hyun Lim, Han Gyu Joo Annals of Nuclear Energy Numerical AnalysisElectrical EngineeringEngineeringEnergy EfficiencyNumerical Simulation	2016	11

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