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Ching-Sheng Lin
Ching-Sheng Lin
在 inl.gov 的电子邮件经过验证
标题
引用次数
引用次数
年份
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
292020
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
102022
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
92016
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
82023
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
62019
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
52022
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
42020
Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimization
CS Lin
Purdue University, 2018
42018
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
42017
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
32022
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
32020
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
22021
Nrc multiphysics analysis capability deployment (fy2021-part 2)
CM Mueller, CS Lin, J Ortensi
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021
22021
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
22019
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
22016
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
22015
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
12016
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
12014
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
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