| Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout Z Guo, R Dailey, T Feng, Y Zhou, Z Sun, ML Corradini, J Wang Reliability Engineering & System Safety 213, 107770, 2021 | 43 | 2021 |
| Effect of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout Z Guo, R Dailey, Y Zhou, Z Sun, J Wang, ML Corradini Nuclear Engineering and Design 372, 110979, 2021 | 24 | 2021 |
| Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out T Feng, J Wang, Y Zhou, P Song, M Wang, R Dailey, W Tian, ... Nuclear Engineering and Design 363, 110678, 2020 | 20 | 2020 |
| Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8. 6 UDGC J Wang, R Dailey, Z Guo, Y Zhou, P Humrickhouse, ML Corradini Nuclear Engineering and Design 371, 110974, 2021 | 14 | 2021 |
| Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model Z Ma, CB Davis, C Parisi, RL Boring PhD, S Zhang, H Zhang, R Dailey, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019 | 10 | 2019 |
| Engineering-level system code for severe accident analysis: MELCOR T Feng, J Wang, X Li, R Dailey, G Vayssier Nuclear Power Plant Design and Analysis Codes, 417-435, 2021 | | 2021 |
