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Vefa N. Kucukboyaci
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Proceedings Papers

CFD Analysis of Thermal Mixing and Mass Flux Distribution in the PWR After MSLB

Hong Xu, Yiban Xu, Liping Cao, Yixing Sung, Vefa N. Kucukboyaci, Richard F. Wright
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A048, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67345
https://doi.org/10.1115/ICONE25-67345
View Paper titled, CFD Analysis of Thermal Mixing and Mass Flux Distribution in the PWR After MSLB
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Topics: Computational fluid dynamics, Pressurized water reactors, Flow (Dynamics), Simulation, Nuclear reactor coolants, Reactor vessels, Coolants, Design, Fuels, Modeling
Proceedings Papers

VERA-CS Modeling and Simulation of PWR Main Steam Line Break Core Response to DNB

Vefa N. Kucukboyaci, Yixing Sung, Yiban Xu, Liping Cao, Robert K. Salko
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A026, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60865
https://doi.org/10.1115/ICONE24-60865
View Paper titled, VERA-CS Modeling and Simulation of PWR Main Steam Line Break Core Response to DNB
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Topics: Modeling, Pressurized water reactors, Simulation, Steam, Flow (Dynamics), Computational fluid dynamics, Fuels, Temperature, Accidents, Boundary-value problems
Journal Articles

COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Vefa N. Kucukboyaci, Liping Cao, Yixing Sung
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031002.
Paper No: NERS-15-1018
https://doi.org/10.1115/1.4032594
Published Online: June 17, 2016
View Article titled, COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
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Topics: Accidents, Coolants, Critical heat flux, Fuel rods, Fuels, Heat transfer, Irradiation (Radiation exposure), Pressurized water reactors, Simulation, Transients (Dynamics)
Proceedings Papers

COBRA-TF Simulation of Fuel Thermal Response During Reactivity Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Vefa N. Kucukboyaci, Liping Cao, Yixing Sung
Proc. ASME. IMECE2014, Volume 6B: Energy, V06BT07A027, November 14–20, 2014
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2014-38513
https://doi.org/10.1115/IMECE2014-38513
View Paper titled, COBRA-TF Simulation of Fuel Thermal Response During Reactivity Initiated Accidents Using the NSRR Pulse Irradiation Experiments
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Topics: Accidents, Fuels, Irradiation (Radiation exposure), Simulation, Fuel rods, Transients (Dynamics), Coolants, Physics, Safety, Boiling
Proceedings Papers

LOCA Break Spectrum Analysis of the Westinghouse Small Modular Reactor

Vefa N. Kucukboyaci, Jun Liao
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A075, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16884
https://doi.org/10.1115/ICONE21-16884
View Paper titled, LOCA Break Spectrum Analysis of the Westinghouse Small Modular Reactor
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Topics: Emission spectroscopy, Small modular reactors, Spectroscopy, Safety, Design, Pressurized water reactors, Reactor vessels, Accidents, Boilers, Containment
Proceedings Papers

Modeling Passive Safety in the Westinghouse Small Modular Reactor: Assessment of Wall Condensation and CMT Natural Circulation

Jun Liao, Vefa N. Kucukboyaci
Proc. ASME. HT2013, Volume 4: Heat and Mass Transfer Under Extreme Conditions; Environmental Heat Transfer; Computational Heat Transfer; Visualization of Heat Transfer; Heat Transfer Education and Future Directions in Heat Transfer; Nuclear Energy, V004T19A004, July 14–19, 2013
Publisher: American Society of Mechanical Engineers
Paper No: HT2013-17742
https://doi.org/10.1115/HT2013-17742
View Paper titled, Modeling Passive Safety in the Westinghouse Small Modular Reactor: Assessment of Wall Condensation and CMT Natural Circulation
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Topics: Condensation, Modeling, Safety, Small modular reactors, Design, Containment, Accidents, Coolants, Gravity (Force), Heat sinks