| Hydrogen in zirconium alloys: A review AT Motta, L Capolungo, LQ Chen, MN Cinbiz, MR Daymond, DA Koss, ... Journal of Nuclear Materials 518, 440-460, 2019 | 328 | 2019 |
| The influence of stress state on the reorientation of hydrides in a zirconium alloy MN Cinbiz, DA Koss, AT Motta Journal of Nuclear Materials 477, 157-164, 2016 | 65 | 2016 |
| Computational fluid dynamics modeling of momentum transport in rotating wall perfused bioreactor for cartilage tissue engineering MN Cinbiz, RS Tığlı, IG Beşkardeş, M Gümüşderelioğlu, Ü Çolak Journal of biotechnology 150 (3), 389-395, 2010 | 46 | 2010 |
| In situ synchrotron X-ray diffraction study of hydrides in Zircaloy-4 during thermomechanical cycling MN Cinbiz, DA Koss, AT Motta, JS Park, JD Almer Journal of Nuclear Materials 487, 247-259, 2017 | 39 | 2017 |
| Failure behavior of SiC/SiC composite tubes under strain rates similar to the pellet-cladding mechanical interaction phase of reactivity-initiated accidents MN Cinbiz, T Koyanagi, G Singh, Y Katoh, KA Terrani, NR Brown Journal of Nuclear Materials 514, 66-73, 2019 | 38 | 2019 |
| Nanoindentation study of bulk zirconium hydrides at elevated temperatures MN Cinbiz, M Balooch, X Hu, A Amroussia, K Terrani Journal of Alloys and Compounds 726, 41-48, 2017 | 32 | 2017 |
| A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding MN Cinbiz, NR Brown, KA Terrani, RR Lowden, D Erdman III Annals of Nuclear Energy 109, 396-404, 2017 | 30 | 2017 |
| Characterization of stress-rupture behavior of nuclear-grade C26M2 FeCrAl alloy for accident-tolerant fuel cladding via burst testing P Joshi, B Kombaiah, MN Cinbiz, KL Murty Materials Science and Engineering: A 791, 139753, 2020 | 26 | 2020 |
| Thermal expansion behavior of δ-zirconium hydrides: Comparison of δ hydride powder and platelets MN Cinbiz, X Hu, K Terrani Journal of Nuclear Materials 509, 566-576, 2018 | 26 | 2018 |
| Considerations for hydride moderator readiness in microreactors MN Cinbiz, CN Taylor, E Luther, H Trellue, J Jackson Nuclear Technology 209 (sup1), S136-S145, 2023 | 22 | 2023 |
| Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing B Garrison, MN Cinbiz, M Gussev, K Linton Journal of Nuclear Materials 560, 153488, 2022 | 19 | 2022 |
| Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing F Cappia, K Wright, D Frazer, K Bawane, B Kombaiah, W Williams, ... Journal of Nuclear Materials 569, 153881, 2022 | 18 | 2022 |
| Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions NR Brown, BE Garrison, RR Lowden, MN Cinbiz, KD Linton Journal of Nuclear Materials 539, 152352, 2020 | 18 | 2020 |
| An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading MN Cinbiz, M Gussev, K Linton, KA Terrani Annals of Nuclear Energy 127, 30-38, 2019 | 18 | 2019 |
| Report on Design and Failure Limits of SiC/SiC and FeCrAl ATF Cladding Concepts under RIA MN Cinbiz, N Brown, RR Lowden, MN Gussev, KD Linton, KA Terrani Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 14 | 2018 |
| Robust deep learning framework for constitutive relations modeling QJ Li, MN Cinbiz, Y Zhang, Q He, G Beausoleil II, J Li Acta Materialia 254, 118959, 2023 | 13 | 2023 |
| Tensile behavior and microstructural evolution of a Fe-25Ni-20Cr austenitic stainless steel (alloy 709) from room to elevated temperatures through in-situ synchrotron X-ray … Y Zhao, MN Cinbiz, JS Park, J Almer, D Kaoumi Journal of Nuclear Materials 540, 152367, 2020 | 12 | 2020 |
| Structure of the pellet-cladding interaction layer of a high-burnup Zr-Nb-O nuclear fuel cladding X Liu, MN Cinbiz, B Kombaiah, L He, F Teng, E Lacroix Journal of Nuclear Materials 556, 153196, 2021 | 11 | 2021 |
| Hydride reorientation in zircaloy-4 under different states of stress as studied with in situ X-ray diffraction MN Cinbiz, AT Motta, D Koss, M Billone Zirconium in the Nuclear Industry: 18th International Symposium, ASTM …, 2018 | 11 | 2018 |
| The impacts of charge transfer, localization, and metallicity on hydrogen retention and transport capacity A Sundar, Y Huang, J Yu, MN Cinbiz International Journal of Hydrogen Energy 47 (46), 20194-20204, 2022 | 10 | 2022 |
