Get started
Author

Kyle W. Ross

Observed names: K. Ross, K. W. Ross, Kyle Ross, Ross, Kyle
OpenAlex ID: A5108348790
State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios
2021 · S. Tina Ghosh, Hossein Esmaili, et al. · Nuclear Technology · 10
MELCOR Computer Code Manuals Volume 3: MELCOR Assessment Problems [Draft]
2015 · Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States), Larry Humphries, et al. · 9
Experimental Validation of CFD Analyses for Estimating the Transport Fraction of LOCA-Generated Insulation Debris to ECCS Sump Screens
2004 · Arup K. Maji, Bruce Letellier, et al. · Nuclear Technology · 6
SOARCA uncertainty analysis of a short-term station blackout accident at the Sequoyah nuclear power plant
2020 · N.E. Bixler, M. Dennis, et al. · Annals of Nuclear Energy · 5
PDF
MELCOR 1.8.5 Simulation of TMI-2 Phase 2 With an Enhanced 2-Dimensional In-Vessel Natural Circulation Model
2002 · Randall O. Gauntt, Kyle Ross, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 3
SOARCA Peach Bottom Atomic Power Station long-term station blackout uncertainty analysis MACCS2 parameters and probabilistic results
2013 · Douglas Osborn, Randall O. Gauntt, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
Terry Turbopump Analytical Modeling Efforts in Fiscal Year 2017 (Progress Report)
2018 · Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States), Jeffrey Cardoni, et al. · 1
Terry Turbopump Expanded Operating Band
2017 · Douglas M. Osborn, Kyle Ross, et al. · 1
PDF
Estimating Safety Valve Stochastic Failure-to-Close Probabilities for the Purpose of Nuclear Reactor Severe Accident Analysis
2017 · S. Tina Ghosh, Alfred Hathaway, et al. · 1
Use of a Real-Time RELAP5 Model to Dynamically Test a Digital Feedwater Control System for a Boiling Water Reactor
1995 · J. A. Mowrey, S. I. Abdel-Khalik, et al. · Nuclear Technology · 1
Computational Modeling of Terry Turbine Airflow Testing to Support the Expansion of Operating Band in Beyond Design Basis Conditions
2021 · Lindsay Gilkey, Nathan Andrews, et al.
Computational Modeling of Terry Turbine Airflow Testing to Support the Expansion of Operating Band in Beyond Design Basis Conditions
2020 · Lindsay N. Gilkey, Nathan Andrews, et al.
PDF
MELCOR Application PRA.
2020 · Ross, Kyle · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Terry Turbopump Analytical Modeling Efforts in Fiscal Year 2018. Progress Report
2018 · Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States), Jeffrey Cardoni, et al.
Rcic Governing Equation Scoping Studies for Severe Accidents.
2015 · Jeffrey N Cardoni, Kyle Ross · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
PDF
RCIC Governing Equation Scoping Studies.
2015 · Jeffrey N Cardoni, Kyle Ross, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
PDF
SOARCA Surry Power Station Uncertainty Analysis: Parameter Methodology and Insights
2014 · Joseph A. Jones, Douglas Osborn, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
PDF
SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Knowledge Advancement
2014 · Randall O. Gauntt, Patrick D. Mattie, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
PDF
MELCOR/MACCS2 Analysis for BWR Mark-I Filtered Containment Venting.
2013 · Douglas Osborn, Kyle Ross, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
MACCS2 Consequence Analysis for BWR Mark I and Mark II Filtered Containment Venting
2012 · USDOE National Nuclear Security Administration (NNSA), Douglas Osborn, et al.
PDF
Radionuclide inventories : ORIGEN2.2 isotopic depletion calculation for high burnup low-enriched uranium and weapons-grade mixed-oxide pressurized-water reactor fuel assemblies.
2010 · Randall Gauntt, Kyle Ross, et al.
PDF
Separate Effects Tests to Quantify Debris Transport to the Sump Screen
2004 · A. K. Maji, D. V. Rao, et al. · Nuclear Safety
TRAC modeling of the K-reactor neutron poison injection system
1994 · David C. Thoman, Kyle Ross, et al. · Transactions of the American Nuclear Society
Works count: 23
Citation count: 39
H-index: 4
I10-index: 1
Year
Topic
Type