An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis CS Lin, WS Yang Nuclear Engineering and Technology 52 (12), 2733-2742, 2020 | 29 | 2020 |
Multiphysics Simulation of the NASA SIRIUS-CAL Fuel Experiment in the Transient Test Reactor Using Griffin T Jing, S Schunert, VM Labouré, MD DeHart, CS Lin, J Ortensi Energies 15 (17), 6181, 2022 | 10 | 2022 |
A moderated target design for minor actinide transmutation in sodium-cooled fast reactor T Park, CS Lin, WS Yang Annals of Nuclear Energy 98, 178-190, 2016 | 9 | 2016 |
Automated power-following control for nuclear thermal propulsion startup and shutdown using MOOSE-based applications VM Labouré, S Schunert, S Terlizzi, ZM Prince, J Ortensi, CS Lin, ... Progress in Nuclear Energy 161, 104710, 2023 | 8 | 2023 |
Application of integrated modeling and simulation capabilities for full scale multiphysics simulation of microreactor concepts P Sabharwall, CS Lin, J Hansel, V Laboure, D Andrs, W Hoffman, ... Idaho National Laboratory, 2019 | 6 | 2019 |
Preliminary conceptual design of fast neutron spectrum nuclear thermal rocket cores using monolithic uranium nitride fuel GJ Youinou, CS Lin Progress in Nuclear Energy 149, 104237, 2022 | 5 | 2022 |
Nuclear thermal propulsion scoping analysis of fuel plate core configurations GJ Youinou, CS Lin, A Abou-Jaoude, CJ Jesse Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020 | 4 | 2020 |
Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimization CS Lin Purdue University, 2018 | 4 | 2018 |
Core design studies of a fast reactor and accelerator-driven system for two-stage fast spectrum fuel cycle option CS Lin, T Park, WS Yang Nuclear Technology 197 (1), 29-46, 2017 | 4 | 2017 |
Automated Control for Nuclear Thermal Propulsion Start-Up using MOOSE-based Applications VM Laboure, S Schunert, S Terlizzi, ZM Prince, J Ortensi, CS Lin, ... Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2022 | 3 | 2022 |
Design and Analysis of a 250 MW Plate-fuel Reactor for Nuclear Thermal Propulsion CS Lin, GJ Youinou Nuclear and Emerging Technologies for Space 2020, 2020 | 3 | 2020 |
Modelling Nuclear Thermal Propulsion Reactor Startup Transients NM Higgins, S Schunert, S Terlizzi, CS Lin, VM Laboure, MD DeHart Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021 | 2 | 2021 |
Nrc multiphysics analysis capability deployment (fy2021-part 2) CM Mueller, CS Lin, J Ortensi Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021 | 2 | 2021 |
Integrated Modeling and Simulation Capability for Full Scale Multi-Physics Simulation and Visualization of MicroReactor Concept P Sabharwall, CS Lin, JE Hansel, V Laboure, D Andrs, WM Hoffman, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019 | 2 | 2019 |
A Two-Stage Fast Spectrum Fuel Cycle Option for Optimum Resource Utilization and Waste Management CS Lin, JS Hader, TK Park, WS Yang Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP 2016), San …, 2016 | 2 | 2016 |
Design of a Low-Enriched Uranium Fast Reactor for Maximum Fuel Resource Utilization CS Lin, JS Hader, TK Park, WS Yang Trans. Am. Nucl. Soc. 113, 1103-1106, 2015 | 2 | 2015 |
Final Report on Two-Stage Fast Spectrum Fuel Cycle Options WS Yang, CS Lin, JS Hader, TK Park, P Deng, G Yang, YS Jung, TK Kim, ... Purdue Univ., West Lafayette, IN (United States), 2016 | 1 | 2016 |
Development of Fuel Cycle Data Packages for Two-Stage Fast Reactor Fuel Cycle Options for Optimum Resource Utilization and Waste Management WS Yang, CS Lin, JS Hader, YS Jung PU/NE-14/13, Purdue University, 2014 | 1 | 2014 |
Transient Simulation of Nuclear Thermal Fuel Specimens in TREAT S Schunert, T Jing, MD DeHart, VM Labouré, CS Lin Transactions of the American Nuclear Society 126, 292-295, 2022 | | 2022 |
Neutronics studies on LEU-fueled fast spectrum core for nuclear propulsion CS Lin, G Youinou Transactions of the American Nuclear Society 124 (1), 13-16, 2021 | | 2021 |