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Browsing by Author Ozceyhan Veysel
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2004
5-Ramaḍān-1424
Calculations of maximum temperature in centerline of nuclear fuel rod and fissile fuel enrichment in hybrid reactor
Ipek Osman
;
Ozceyhan Veysel
;
Yapici Huseyin
524
0
2000
21-Rajab-1420
Numerical neutronic analysis of a natural lithium cooled fusion breeder fueled with UO2
Yapici Huseyin
;
Ozceyhan Veysel
374
130
1999
10-Rajab-1419
Pertinent integral data per fusion neutron in infinite medium
Sahin Sumer
;
Yapici Huseyin
;
Ozceyhan Veysel
413
172
Showing results 1 to 3 of 3