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Yeon Sang Jung

2.0 - MOOSE: Enabling massively parallel multiphysics simulation
2022 · Alexander D. Lindsay, Derek R. Gaston, et al. · SoftwareX · 247
3.0 - MOOSE: Enabling massively parallel multiphysics simulations
2024 · Guillaume Giudicelli, Alexander Lindsay, et al. · SoftwareX · 187
Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers
2013 · Yeon Sang Jung, Cheon Bo Shim, et al. · Annals of Nuclear Energy · 183
Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code
2015 · Min Ryu, Yeon Sang Jung, et al. · Journal of Nuclear Science and Technology · 74
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Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors
2024 · Yaqi Wang, Zachary M. Prince, et al. · Annals of Nuclear Energy · 58
Griffin Software Development Plan
2021 · Changho Lee, Yeon Jung, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 55
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MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries
2023 · Emily Shemon, Yinbin Miao, et al. · Nuclear Science and Engineering · 37
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PROTEUS-MOC User Manual
2018 · Argonne National Lab. (ANL), Argonne, IL (United States), Yeon Jung, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 29
Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC
2019 · Guangchun Zhang, Albert Hsieh, et al. · Nuclear Science and Engineering · 25
A Consistent CMFD Formulation for the Acceleration of Neutron Transport Calculations Based on the Finite Element Method
2017 · Yeon Sang Jung, Won Sik Yang · Nuclear Science and Engineering · 20
Application of Backward Differentiation Formula to Spatial Reactor Kinetics Calculation With Adaptive Time Step Control
2011 · Cheon-Bo Shim, Yeon-Sang Jung, et al. · Nuclear Engineering and Technology · 19
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PROTEUS-NODAL User Manual
2018 · Yeon Jung, USDOE Office of Nuclear Energy (NE), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 18
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MC2-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis Nuclear
2018 · Changho Lee, Yeon Sang Jung, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 18
Temperature dependent subgroup formulation with number density adjustment for direct whole core power reactor calculation
2016 · Yeon Sang Jung, Chang Hyun Lim, et al. · Annals of Nuclear Energy · 13
Implementation of the transient fixed-source problem in the neutron transport code PROTEUS-MOC
2019 · Tat Nghia Nguyen, Yeon Sang Jung, et al. · Annals of Nuclear Energy · 12
Performance Improvements for the Griffin Transport Solvers
2021 · Yaqi Wang, Zachary Prince, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 11
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Micro Reactor Simulation Using the PROTEUS Suite in FY19
2019 · Chang-ho Lee, USDOE Office of Nuclear Energy - Nuclear Energy Advanced Modeling and Simulation (NEAMS), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 11
Generation of the Cross Section Library for PROTEUS
2018 · Changho Lee, USDOE Office of Nuclear Energy (NE), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 10
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MOOSE Framework Meshing Enhancements to Support Reactor Analysis
2021 · E. Shemon, Y. Jung, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 9
Development of the PROTEUS and ANSYS Coupled System for Simulating Heat Pipe Cooled Micro Reactors
2020 · Changho Lee, USDOE, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 9
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Verification of the nTRACER/CTF code system for full core high resolution cycle analysis with the OECD/NEA TVA Watts Bar Unit 1 benchmark
2025 · Sung Joon Kwon, Marianna Papadionysiou, et al. · Annals of Nuclear Energy · 8
MOOSE Framework Enhancements for Meshing Reactor Geometries
2022 · Emily Shemon, Kun Mo, et al. · International Conference on Physics of Reactors (PHYSOR) · 8
Development of a Novel Test Method for On-Demand Internal Short Circuit in a Li-Ion Cell (Presentation)
2011 · Matthew Keyser, Dirk Long, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 8
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Extension and Demonstration of NEAMS Multiphysics Tools to Lead-Cooled, Sodium-Cooled, and Molten Salt Fast Reactor Applications
2019 · Emily Shemon, USDOE Office of Nuclear Energy (NE), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 7
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High-Fidelity Simulation of the Empire Microreactor Benchmark Problem Using Griffin with Online Cross Section Generation
2024 · Changho Lee, Hansol Park, et al. · Nuclear Science and Engineering · 5
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Works count: 71
Citation count: 1,164
H-index: 13
I10-index: 18
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