| Purex co-processing of spent LWR fuels: flow sheet OH Zabunogˇlu, L Özdemir Annals of Nuclear Energy 32 (2), 151-162, 2005 | 36 | 2005 |
| Determination of fissile fraction in MOX (mixed U+ Pu oxides) fuels for different burnup values L Özdemir, BB Acar, OH Zabunoğlu Annals of Nuclear Energy 38 (2-3), 540-546, 2011 | 14 | 2011 |
| Purex co-processing of spent LWR fuels: comparative fuel cycle cost analyses OH Zabunoğlu, L Özdemir Annals of Nuclear Energy 32 (2), 137-149, 2005 | 8 | 2005 |
| Burnup analysis, natural U requirement and nuclear resource utilization in a combined PWR-CANDU system: Complete coprocessing and DUPIC scenarios L Özdemir, E Çağlak, A Tezbaşaran, OH Zabunoğlu Progress in Nuclear Energy 91, 140-146, 2016 | 4 | 2016 |
| Application of CNUREAS and MCNP5 codes to VVER-1000 MOX Core Computational Benchmark SŞ Lüle, L Özdemir, A Erdoğan Progress in Nuclear Energy 85, 454-461, 2015 | 4 | 2015 |
| PWR-CANDU6 BİRLEŞİK YAKIT ÇEVRİMİ VE CANDU6’DA URANYUM+ TORYUM KULLANIMI L Özdemir Fen Bilimleri Enstitüsü, 2017 | | 2017 |
| VVER-1000 reaktöründe MCNP5/MONTEBURNS Monte Carlo kodları ile yanma oranı hesaplamaları L Özdemir Türkiye Atom Enerjisi Kurumu, 2016 | | 2016 |
| Burnup calculations of TR-2 research reactor with monteburns Monte Carlo code L Özdemir, A Erdoğan, S Şentürk Lüle | | 2012 |
| Burnup calculations of TR-2 research reactor: MONTEBURNS simulations and experimental verifications L Özdemir, A Erdoğan, S Şentürk Lüle | | 2010 |
