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William A. Byers

Observed names: W. A. Byers, W. Byers, W.A. Byers, William Byers
ORCID: 0000-0003-2655-4856
Observed ORCID: 0000-0003-2655-4856
OpenAlex ID: A5004822547
Westinghouse eVinci™ Heat Pipe Micro Reactor Technology Development
2021 · Matt M. Swartz, William A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 53
Deposition and characterization of conducting polymer thin films on insulating substrates
1995 · K.F. Schoch, W.A. Byers, et al. · Synthetic Metals · 42
The fractalline properties of experimentally simulated PWR fuel crud
2017 · I. Dumnernchanvanit, V.K. Mishra, et al. · Journal of Nuclear Materials · 18
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Solubility of Lithium Monoborate in High-Temperature Water
2000 · W. A. Byers, W. T. Lindsay, et al. · Journal of Solution Chemistry · 18
Plasma polymerized tetramethyl germanium films deposited at elevated substrate temperatures
1993 · R. K. Sadhir, H. E. Saunders, et al. · Polymer Engineering and Science · 18
Westinghouse Advanced Loop Tester (WALT) Update
2008 · G. Wang, W. A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 13
Simulation of PWR Crud
2014 · W. A. Byers, G. Wang, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 12
Thermal Conductivity Measurements for Simulated PWR Crud
2013 · G. Wang, W. A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 11
Pressurized Water Reactor Core Crud Mapping
2010 · W. A. Byers · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 8
Single Rod Heat Transfer Tests to Study the Effects of Crud Deposition
2006 · G. Wang, W. A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 7
Methods to Reduce CIPS/CILC Risk for the Zero Fuel Failure by 2010 Initiative
2010 · Guoqiang Wang, Michael Y. Young, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 4
Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding
2022 · William A. Byers, Guoqiang Wang · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 3
Effects of Cold Spray Chromium Coatings on the Properties of Zirconium Alloys
2021 · Jorie L. Walters, Javier E. Romero, et al. · 3
ICONE15-10665 VIPRE-01/BOA Modeling of Westinghouse Advanced Loop Tester (WALT)
2007 · G. Wang, M. Y. Young, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 3
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Use of Chromium Coating to Provide Protection of Zirconium Cladding at DNB Conditions
2022 · Zeses Karoutas, Dave Mitchell, et al. · TopFuel Light Water Reactor Fuel Performance Conference (TopFuel) · 2
Testing of Silicon Carbide as a Nuclear Fuel Cladding
2022 · Luke Czerniak, Ed Lahoda, et al. · TopFuel Light Water Reactor Fuel Performance Conference (TopFuel) · 1
UHT Test Facility Updates and Oxidation Tests for Accident Tolerant Fuel Development
2021 · William A. Byers, Guoqiang Wang · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
WATCH Loop Development and Commissioning Tests
2018 · W. A. Byers, G. Wang · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
ICONE19-43627 Best Estimate Probabilistic Safety Assessment Results for the Westinghouse Advanced Loop Tester (WALT)
2011 · Guoqiang Wang, William A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
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VIPRE-01/BOA modeling of Westinghouse advanced loop tester (WALT)
2007 · G Wang, Michael Y. Young, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
Plasma deposited aluminum nitride films
1986 · R. K. Sadhir, W. A. Byers · IEEE Conference on Electrical Insulation and Dielectric Phenomena (CEIDP) · 1
Detection of Boiling in Fuel Assembly Components Using the Pressure Noise Correlation Technique
2025 · W. A. Byers, Yiban Xu · Springer proceedings in physics
Background and Status of the Aluminum Spent Nuclear Fuel Remote Canister Monitoring Project
2025 · Evans D. Kitcher, Jorge V. Carvajal, et al. · SSRN Electronic Journal
ATF Coating Response in KOH Adjusted PWR Water -- Under Extended Exposure
2022 · R. Ratnayake, D. Hussey, et al. · TopFuel Light Water Reactor Fuel Performance Conference (TopFuel)
Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development
2021 · Guoqiang Wang, William A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Works count: 33
Citation count: 221
H-index: 8
I10-index: 8
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