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Mehtap Gunay
Mehtap Gunay
Undergraduate of Computer Science, Istanbul Şehir University
Verified email at std.sehir.edu.tr
Title
Cited by
Cited by
Year
Three-dimensional neutronic calculations for the fusion breeder Apex reactor
B Şarer, M Günay, ME Korkmaz, A Hançerlioğullari
Fusion science and technology 52 (1), 107-115, 2007
37*2007
Calculations of neutron-induced production cross-sections of 180,182,183,184,186 W up to 20 MeV
B Şarer, A Aydın, M Günay, ME Korkmaz, E Tel
Annals of Nuclear Energy 36 (4), 417-426, 2009
292009
The effect on neutronic calculations of certain alternative fuels in a boiling water reactor by using MCNPX Monte Carlo method
M Günay, V Sanchez Espinoza, A Travleev
Acta Physica Polonica A 128 (2B), 2015
42015
Impact of different physics models in MCNPX code on the neutron and proton heating in ADS
B Sarer, S Sahin, M Gunay
Transactions of the American Nuclear Society 106, 28-31, 2012
12012
Radiation Damage Investigation on Certain Alternative Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code
M Günay
Acta Physica Polonica A 128 (2B), 2015
2015
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