| Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4 RV Umretiya, B Elward, D Lee, M Anderson, RB Rebak, JV Rojas Journal of Nuclear Materials 541, 152420, 2020 | 83 | 2020 |
| Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials D Lee, B Elward, P Brooks, R Umretiya, J Rojas, M Bucci, RB Rebak, ... Applied Thermal Engineering 185, 116347, 2021 | 33 | 2021 |
| Oxidation resistance in 1200° C steam of a FeCrAl alloy fabricated by three metallurgical processes AK Hoffman, RV Umretiya, VK Gupta, M Larsen, C Graff, C Perlee, ... JOM 74 (4), 1690-1697, 2022 | 24 | 2022 |
| Effect of aluminum on the FeCr (Al) alloy oxidation resistance in steam environment at low temperature (400 C) and high temperature (1200 C) A Chikhalikar, I Roy, H Abouelella, R Umretiya, A Hoffman, M Larsen, ... Corrosion Science 209, 110765, 2022 | 23 | 2022 |
| Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material RV Umretiya, S Vargas, D Galeano, R Mohammadi, CE Castano, ... Journal of Nuclear Materials 535, 152163, 2020 | 23 | 2020 |
| Elucidating precipitation in FeCrAl alloys through explainable AI: A case study SK Ravi, I Roy, S Roychowdhury, B Feng, S Ghosh, C Reynolds, ... Computational Materials Science 230, 112440, 2023 | 18 | 2023 |
| Understanding oxidation of Fe-Cr-Al alloys through explainable artificial intelligence I Roy, B Feng, S Roychowdhury, SK Ravi, RV Umretiya, C Reynolds, ... MRS communications 13 (1), 82-88, 2023 | 17 | 2023 |
| Data-driven predictive modeling of FeCrAl oxidation I Roy, S Roychowdhury, B Feng, SK Ravi, S Ghosh, R Umretiya, ... Materials Letters: X 17, 100183, 2023 | 16 | 2023 |
| On Uncertainty Quantification in Materials Modeling and Discovery: Applications of GE's BHM and IDACE SK Ravi, A Bhaduri, A Amer, S Ghosh, L Wang, A Hoffman, R Umretiya, ... AIAA SCITECH 2023 Forum, 2023 | 16 | 2023 |
| FeCrAl fuel/clad chemical interaction in light water reactor environments HJ Qu, M Higgins, H Abouelella, F Cappia, J Burns, L He, C Massey, ... Journal of Nuclear Materials 587, 154717, 2023 | 15 | 2023 |
| Effect of nickel on the oxidation behavior of FeCrAl alloy in simulated PWR and BWR conditions HJ Qu, H Abouelella, AS Chikhalikar, R Rajendran, I Roy, J Priedeman, ... Corrosion Science 216, 111093, 2023 | 15 | 2023 |
| Effect of Al concentration on Fe-17Cr alloy during steam oxidation at 400° C I Roy, H Abouelella, R Rajendran, AS Chikhalikar, M Larsen, R Umretiya, ... Corrosion Science 217, 111135, 2023 | 12 | 2023 |
| The relationship between grain size distribution and ductile to brittle transition temperature in FeCrAl alloys AK Hoffman, RV Umretiya, C Crawford, I Spinelli, S Huang, S Buresh, ... Materials Letters 331, 133427, 2023 | 10 | 2023 |
| Effect of molybdenum on the oxidation resistance of FeCrAl alloy in lower temperature (400° C) and higher temperature (1200° C) steam environments HJ Qu, AS Chikhalikar, H Abouelella, I Roy, R Rajendran, BS Nagothi, ... Corrosion Science 229, 111870, 2024 | 9 | 2024 |
| Effect of aging and α’segregation on oxidation and electrochemical behavior of FeCrAl alloys R Rajendran, AS Chikhalikar, I Roy, H Abouelella, HJ Qu, RV Umretiya, ... Journal of Nuclear Materials 588, 154751, 2024 | 9 | 2024 |
| Surface characteristics of accident tolerant fuels cladding and their potential impact in critical heat flux R Umretiya, D Ginestro, SB y Leon, J Rojas, B Elward, M Anderson, ... 18th Int. Top. Meet. Nucl. React. Therm. Hydraul. NURETH 2019, 2019 | 8 | 2019 |
| Optimizing chemistry for designing oxidation resistant FeCrAl alloys I Roy, H Abouelella, RV Umretiya, S Roychowdhury, B Feng, SK Ravi, ... MRS Advances 8 (1), 21-26, 2023 | 6 | 2023 |
| Evolution of microstructure and surface characteristics of FeCrAl alloys when subjected to flow boiling testing RV Umretiya, D Lee, B Elward, M Anderson, RB Rebak, JV Rojas Journal of Nuclear Materials 557, 153269, 2021 | 6 | 2021 |
| Hydrothermal Corrosion of Latest Generation of FeCrAl Alloys for Nuclear Fuel Cladding BS Nagothi, H Qu, W Zhang, RV Umretiya, E Dolley, RB Rebak Materials 17 (7), 1633, 2024 | 5 | 2024 |
| Effect of the redox potential on the general corrosion behavior of industrial nuclear alloys RB Rebak, L Yin, W Zhang, RV Umretiya Journal of Nuclear Materials 576, 154257, 2023 | 5 | 2023 |
