화학공학소재연구정보센터
검색결과 : 5건
No. Article
1 Evaluation of the radiation damage parameters of ODS steel alloys in the first wall of deuterium-tritium fusion-fission (hybrid) reactors
Tunc G, Sahin HM, Sahin S
International Journal of Energy Research, 42(1), 198, 2018
2 Investigation of tritium breeding ratio using different coolant material in a fusion-fission hybrid reactor
Sahin HM, Tunc G, Sahin N
International Journal of Hydrogen Energy, 41(17), 7069, 2016
3 Heat transfer in rectangular microchannels
Tunc G, Bayazitoglu Y
International Journal of Heat and Mass Transfer, 45(4), 765, 2002
4 Heat transfer in microtubes with viscous dissipation
Tunc G, Bayazitoglu Y
International Journal of Heat and Mass Transfer, 44(13), 2395, 2001
5 Study on the fusion reactor performance with different materials and nuclear waste actinides
Sahin S, Sahin HM, Sahiner H, Tunc G
International Journal of Energy Research