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Alper Buğra Arslan
Alper Buğra Arslan
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Año
Neutronic analysis of an ads fuelled with minor actinide and designed for spent fuel enrichment and fissile fuel production
B Durmaz, G Bakir, BA Arslan, H Yapici
Nuclear Technology and Radiation Protection 36 (4), 299-314, 2021
52021
Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System
AB Arslan, I Yilmaz, G Bakir, H Yapici
Science and Technology of Nuclear Installations 2019, 1-13, 2019
32019
Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor
B Durmaz, G Bakir, BA Arslan, H Yapici
Nuclear Technology and Radiation Protection 37 (4), 289-301, 2022
2022
Neutron-induced medical radioisotope production in a conceptual accelerator-driven system, fueled with uranium carbide
A Arslan, G Bakir, S Selçuklu, G Genç, H Yapici
Acta Physica Polonica A 130 (1), 68-71, 2016
2016
CANDU ve PWR reaktörlerinde açığa çıkan kısa ömürlü fisyon ürünlerinin değerlendirilmesi ve uzun ömürlü fisyon ürünlerinin hızlandırıcı sürücülü sistemde dönüştürülmesi
AB Arslan
Fen Bilimleri Enstitüsü, 0
El sistema no puede realizar la operación en estos momentos. Inténtalo de nuevo más tarde.
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