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Jeffrey W. Lane

Observed names: J. Lane, J. W. Lane, Jeffrey Lane
ORCID: 0000-0001-7473-3758
Observed ORCID: 0000-0001-7473-3758
OpenAlex ID: A5073720016
Development and assessment of a nearly autonomous management and control system for advanced reactors
2020 · Linyu Lin, Paridhi Athe, et al. · Annals of Nuclear Energy · 63
A data-driven framework for error estimation and mesh-model optimization in system-level thermal-hydraulic simulation
2019 · Han Bao, Nam T. Dinh, et al. · Nuclear Engineering and Design · 42
Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation
2020 · Han Bao, Nam Dinh, et al. · Annals of Nuclear Energy · 33
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system
2021 · Linyu Lin, Paridhi Athe, et al. · Annals of Nuclear Energy · 29
Benchmark of GOTHIC to EBR-II SHRT-17 and SHRT-45R Tests
2020 · J. W. Lane, J. M. Link, et al. · Nuclear Technology · 20
A self-consistent three-field constitutive model set for predicting co-current annular flow
2010 · Jeffrey W. Lane, David L. Aumiller, et al. · Nuclear Engineering and Design · 17
Hybrid System Level and Coarse Grid CFD Tool for Three-Dimensional Natural Circulation, Mixing, and Stratification Modeling
2021 · R. C. Harvill, J. W. Lane, et al. · Nuclear Technology · 12
Steady-State and Transient Benchmarks of GOTHIC to the Molten Salt Reactor Experiment
2021 · R. C. Harvill, J. W. Lane, et al. · Nuclear Technology · 11
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Coupling Gothic and RELAP5 for Passive Containment Cooling Modeling
2021 · J. C. Kang, J. S. Jeong, et al. · Nuclear Technology · 10
The development of a comprehensive annular flow modeling package for two-phase three-field transient safety analysis codes
2009 · J. W. Lane · PhDT · 9
Development and Assessment of Data-Driven Digital Twins in a Nearly Autonomous Management and Control System for Advanced Reactors
2020 · Linyu Lin, Pascal Rouxelin, et al. · 4
Performance Assessment of the Two-Phase Pump Degradation Model in the RELAP5-3D Transient Safety Analysis Code
2008 · Jeffrey W. Lane, L. E. Hochreiter, et al. · Nuclear Technology · 4
Verification and Validation of Transient Body Force in GOTHIC for Spent Fuel Pool Response to Seismic Events and Other Applications
2021 · P. C. Skelton, J. W. Lane, et al. · Nuclear Technology · 3
Iaea’s Coordinated Research Projects on Thermal Hydraulics of Fast Reactors
2023 · ikoleta Morelová, Vladimir Kriventsev, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2
Development and Assessment of a Nearly Autonomous Management and Control System During a Single Loss of Flow Accident
2020 · Linyu Lin, Paridhi Athe, et al. · 2
LWR Impact on Containment
2019 · J. W. Lane, S. C. Franz · Modern nuclear energy analysis methods · 1
Performance Assessment of the Two-Phase Pump Degradation Model in the RELAP5-3D Transient Safety Analysis Code
2006 · J. W. Lane, L. E. Hochreiter, et al. · Transactions of the American Nuclear Society · 1
Benchmarking GOTHIC to the Molten Salt Reactor Experiment
2019 · A. Gates, R. Harvill, et al.
Large Open Region Interfacial Drag Modeling Package in COBRA-IE
2016 · David L. Aumiller, Jeffrey W. Lane · Nuclear Science and Engineering
Uncertainty methodology for the strongly coupled physical phenomena associated with annular flow
2012 · J. W. Lane, D. L. Aumiller · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Three-Field Countercurrent Flow Limitation Model
2012 · Jeffrey W. Lane, David L. Aumiller, et al. · Nuclear Technology
Three-Field Annular Flow Modeling Package-Part II: Entrainment Rate Models
2010 · J. W. Lane, D. L. Aumiller, et al. · Transactions of the American Nuclear Society
Three-Field Annular Flow Modeling Package - Part I: Interfacial Structure and Drag
2010 · J. W. Lane, D. L. Aumiller, et al. · Transactions of the American Nuclear Society
Three-Field Counter-Current Flow Limitation (CCFL) Model
2009 · J. W. Lane, D. L. Aumiller, et al. · Transactions of the American Nuclear Society
Works count: 24
Citation count: 263
H-index: 9
I10-index: 9
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