| A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding B Qiu, J Wang, Y Deng, M Wang, Y Wu, SZ Qiu Nuclear Engineering and Technology 52 (1), 1-13, 2020 | 89 | 2020 |
| Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs Y Deng, Y Wu, B Qiu, D Zhang, M Wang, W Tian, S Qiu, GH Su Annals of Nuclear Energy 104, 146-156, 2017 | 42 | 2017 |
| Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response Y Deng, K Shirvan, Y Wu, G Su Journal of Nuclear Materials 507, 24-37, 2018 | 39 | 2018 |
| Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs Y Deng, Y Wu, D Zhang, W Tian, S Qiu, GH Su Nuclear Engineering and Design 301, 353-365, 2016 | 37 | 2016 |
| Liquid metal embrittlement of an Fe10Cr4Al ferritic alloy exposed to oxygen-depleted and-saturated lead-bismuth eutectic at 350° C X Gong, J Chen, F Hu, C Xiang, Z Yu, J Xiao, H Wang, H Gong, H Wang, ... Corrosion Science 165, 108364, 2020 | 36 | 2020 |
| Liquid metal embrittlement susceptibility of a high-entropy alloy exposed to oxygen-depleted liquid lead-bismuth eutectic at 250 and 350 C X Huang, X Gong, M Song, J Chen, F Hu, Y Yin, J Xiao, H Wang, H Wang, ... Journal of Nuclear Materials 528, 151859, 2020 | 31 | 2020 |
| Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element Y Deng, Y Wu, Y Li, D Zhang, W Tian, GH Su, S Qiu Annals of Nuclear Energy 94, 44-54, 2016 | 31 | 2016 |
| A comparative study on preliminary performance evaluation of ATFs under normal and accident conditions with FRAP-ATF code B Qiu, Y Wu, Y Deng, Y He, T Liu, GH Su, W Tian Progress in Nuclear Energy 105, 51-60, 2018 | 30 | 2018 |
| Creep failure of a solution-annealed 15-15Ti steel exposed to stagnant lead-bismuth eutectic at 550 and 600° C X Gong, Z Yang, Y Deng, J Xiao, H Wang, Z Yu, Y Yin Materials Science and Engineering: A 798, 140230, 2020 | 27 | 2020 |
| Utilization of 3D fuel modeling capability of BISON to derive new insights in performance of advanced PWR fuel concepts Y Deng, K Shirvan, Y Wu, G Su Journal of Nuclear Materials 516, 271-288, 2019 | 26 | 2019 |
| Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel Y Deng, Y Wu, D Zhang, Q Lu, W Tian, S Qiu, GH Su Progress in Nuclear Energy 95, 8-22, 2017 | 23 | 2017 |
| 3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition H Liao, Y Wang, Y Li, K Wang, Y Deng, M Su, Y Wu, M Wang, S Qiu Progress in Nuclear Energy 126, 103428, 2020 | 22 | 2020 |
| Upgrade of FROBA code and its application in thermal-mechanical analysis of space reactor fuel Y Deng, Y Wu, C Gong, D Zhang, W Tian, S Qiu, GH Su Nuclear Engineering and Design 332, 297-306, 2018 | 19 | 2018 |
| Effect of temperature on liquid metal embrittlement susceptibility of an Fe10Cr4Al ferritic alloy in contact with stagnant lead-bismuth eutectic X Gong, F Hu, J Chen, H Wang, H Gong, J Xiao, H Wang, Y Deng, B Pang, ... Journal of Nuclear Materials 537, 152196, 2020 | 14 | 2020 |
| Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors X Huang, P Chen, Y Yin, B Pang, Y Li, X Gong, Y Deng Nuclear Engineering and Design 361, 110567, 2020 | 12 | 2020 |
| Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials Y Deng, M Liu, B Qiu, Y Yin, X Gong, X Huang, B Pang, Y Li Nuclear Engineering and Technology 53 (1), 178-187, 2021 | 10 | 2021 |
| Performance evaluation and efficiency enhancement of a space thermionic fuel element for thermal energy conversion and utilization Y Deng, B Qiu, K Lu, Y Yin, X Gong, B Pang, X Huang, Y Li, Y Wu, G Su Applied Thermal Engineering 173, 115237, 2020 | 10 | 2020 |
| An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code P Chen, B Qiu, Y Li, Y Wu, Y Hui, Y Deng, K Zhang Nuclear Engineering and Technology 53 (4), 1236-1249, 2021 | 8 | 2021 |
| Investigation on fuel cracking induced relocation behavior of dual-cooled annular fuel based on finite element simulation Y Deng, B Qiu, Y Yin, Y Wu, G Su Journal of Nuclear Materials 567, 153779, 2022 | 7 | 2022 |
| Research on performance enhancement of nuclear fuel with SiC cladding by using high thermal conductivity fuels Y Deng, B Qiu, B Pang, X Gong, Y Wu, G Su, X Huang, Y Li, Y Yin Progress in Nuclear Energy 124, 103330, 2020 | 7 | 2020 |
