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Vefa N. Kucukboyaci

Observed names: Kucukboyaci, Vefa, V Kucukboyaci, V. Kucukboyaci, V.N. Kucukboyaci, Vefa Kucukboyaci
ORCID: 0000-0002-3474-9277
Observed ORCID: 0000-0002-3474-9277
OpenAlex ID: A5009703029
Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production
2005 · Philip MacDonald, Jacopo Buongiorno, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 45
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Best estimate plus uncertainty analysis of departure from nucleate boiling limiting case with CASL core simulator VERA-CS in response to PWR main steam line break event
2016 · C.S. Brown, H. Zhang, et al. · Nuclear Engineering and Design · 24
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Ctf: A Modernized, Production-Level, Thermal Hydraulic Solver for the Solution of Industry-Relevant Challenge Problems in Pressurized Water Reactors
2022 · Robert Salko, Aaron Wysocki, et al. · SSRN Electronic Journal · 23
Development of a LOCA safety analysis evaluation model for the Westinghouse Small Modular Reactor
2016 · Jun Liao, Vefa N. Kucukboyaci, et al. · Annals of Nuclear Energy · 21
Effectiveness of pentran™'s unique numerics for simulation of the Kobayashi benchmarks
2001 · A. Haghighat, G.E. Sjoden, et al. · Progress in Nuclear Energy · 13
Preliminary LOCA analysis of the westinghouse small modular reactor using the WCOBRA/TRAC-TF2 thermal-hydraulics code
2012 · Jun Liao, Vefa Kucukboyaci, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 8
Transient Analysis of a Micro-Reactor Using the DireWolf Code Suite
2022 · Nathan Roskoff, Vefa Kucukboyaci, et al. · International Conference on Physics of Reactors (PHYSOR) · 7
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VERA-CS Modeling and Simulation of PWR Main Steam Line Break Core Response to DNB
2016 · Vefa N. Kucukboyaci, Yixing Sung, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 6
Modeling and Analysis of a Micro-Reactor Using the DireWolf Code Suite
2022 · Nathan Roskoff, Vefa Kucukboyaci, et al. · International Conference on Physics of Reactors (PHYSOR) · 5
Modeling of BWR for Neutron and Gamma Fields Using PENTRAN™
2001 · V Kucukboyaci, A Haghighat, et al. · 5
CASL COBRA-TF Improvements for PWR DNB Analysis.
2016 · Yixing Sung, Liping Cao, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4
PENTRAN Modeling for Design and Optimization of the Spherical-Shell Transmission Experiments
2001 · Vefa Kucukboyaci, Alireza Haghighat, et al. · Transactions of the American Nuclear Society · 4
New Particle Transport Methods for Design and Optimization of Spherical-Shell Transmission Measurements
2002 · Alireza Haghighat, Shane R. Gardner, et al. · Journal of Nuclear Science and Technology · 3
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Steady-State and Transient Analysis of a Heat-Pipe Cooled Micro-Reactor Using the DireWolf Code Suite
2024 · Tatiana Siaraferas, Vefa Kucukboyaci, et al. · International Conference on Physics of Reactors (PHYSOR) · 2
COBRA-TF Simulation of Fuel Thermal Response During Reactivity Initiated Accidents Using the NSRR Pulse Irradiation Experiments
2014 · Vefa N. Kucukboyaci, Liping Cao, et al. · ASME International Mechanical Engineering Congress and Exposition (IMECE) · 2
Modeling Passive Safety in the Westinghouse Small Modular Reactor: Assessment of Wall Condensation and CMT Natural Circulation
2013 · Jun Liao, Vefa N. Kucukboyaci · ASME Heat Transfer Summer Conference (HT) · 2
Spent fuel pool storage calculations using the ISOCRIT burnup credit tool
2011 · Vefa N. Kucukboyaci, William J. Marshall · Annals of Nuclear Energy · 2
High-fidelity thermal, mechanical, and neutronic analysis of an eVinci-like microreactor using Serpent 2 and OFFBEAT on unstructured meshes
2026 · Chiara Genoni, Fausto Franceschini, et al. · Progress in Nuclear Energy · 1
CFD Analysis of Thermal Mixing and Mass Flux Distribution in the PWR After MSLB
2017 · Hong Xu, Yiban Xu, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
2016 · Vefa N. Kucukboyaci, Liping Cao, et al. · Journal of Nuclear Engineering and Radiation Science · 1
EPRI depletion benchmark calculations using PARAGON
2015 · Vefa N. Kucukboyaci · Annals of Nuclear Energy · 1
LOCA Break Spectrum Analysis of the Westinghouse Small Modular Reactor
2013 · Vefa N. Kucukboyaci, Jun Liao · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
A New Investigation of Iron Cross Sections via Spherical-Shell Transmission Measurements and Particle Transport Calculations
2002 · James M. Adams, Arzu Alpan, et al. · Journal of Nuclear Science and Technology · 1
Performance of PENTRAN™ 3-D Parallel Particle Transport Code on the IBM SP2 and PCTRAN Cluster
2001 · Vefa Kucukboyaci, Alireza Haghighat, et al. · Lecture notes in computer science · 1
Xenon Effects during Power Transient of a Heat-Pipe Cooled Microreactor using the DireWolf Code Suite
2026 · T. Siaraferas, V. Kucukboyaci, et al. · Zenodo (CERN European Organization for Nuclear Research)
Works count: 36
Citation count: 188
H-index: 7
I10-index: 5
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