| Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way Y He, P Chen, Y Wu, GH Su, W Tian, S Qiu Nuclear Engineering and Design 328, 27-35, 2018 | 58 | 2018 |
| 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 |
| Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions Y He, K Shirvan, Y Wu, GH Su Nuclear Engineering and Design 353, 110276, 2019 | 25 | 2019 |
| A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way F Xiang, Y He, Y Niu, C Deng, Y Wu, K Wang, W Tian, G Su, S Qiu Annals of Nuclear Energy 166, 108734, 2022 | 17 | 2022 |
| Automatic differentiation approach for solving one-dimensional flow and heat transfer problems Y Niu, Y He, F Xiang, J Zhang, Y Wu, W Tian, G Su, S Qiu Annals of Nuclear Energy 160, 108361, 2021 | 17 | 2021 |
| 3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM Y Zhou, J Wang, Z Guo, Y He, Y Zhang, S Qiu, GH Su, ML Corradini Progress in Nuclear Energy 138, 103790, 2021 | 16 | 2021 |
| Integrating a multi-layer deformation model in FRAPTRAN for accident Tolerant fuel analysis Y He, K Shirvan, Y Wu, G Su Annals of Nuclear Energy 133, 441-454, 2019 | 15 | 2019 |
| Investigation on thermo-mechanical performance of fully ceramic microencapsulated fuel C Zhang, Y Wu, Y He, Y Li, S Liu, J Zhang, W Tian, GH Su, S Qiu, J Wu Journal of Nuclear Materials 556, 153171, 2021 | 11 | 2021 |
| An effective method for modeling 1D two-phase two-fluid six-equation model with automatic differentiation approach Y Niu, Y He, B Qiu, F Xiang, C Deng, Y Li, J Zhang, Y Wu, W Tian, GH Su, ... Progress in Nuclear Energy 151, 104325, 2022 | 6 | 2022 |
| Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions C Deng, Y He, F Xiang, Y Wu, J Zhang, W Tian, G Su, S Qiu Progress in Nuclear Energy 149, 104265, 2022 | 6 | 2022 |
| Preliminary development of a multi-physics coupled fuel performance code for annular fuel analysis under normal conditions Y He, Y Niu, F Xiang, Y Wu, J Zhang, G Su, W Tian, S Qiu Nuclear Engineering and Design 393, 111810, 2022 | 4 | 2022 |
| Development of a transient module based on FROBA-ROD code and assessment for fuel rod performance under reactivity-initiated accident H Liao, K Lu, C Li, H Yao, Y He, Y Wu, GH Su, S Qiu Annals of Nuclear Energy 160, 108377, 2021 | 4 | 2021 |
| Preliminary prediction for survival time of fuel rod under critical heat flux Y He, K Shirvan, Y Wu, G Su Annals of Nuclear Energy 151, 107896, 2021 | 4 | 2021 |
| Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code H Liao, C Li, Y He, Y Wu, Y Zhang, W Tian, GH Su, S Qiu International Journal of Advanced Nuclear Reactor Design and Technology 3, 54-65, 2021 | 4 | 2021 |
| Coupled neutronics, thermal-hydraulics, and fuel performance analysis of dispersion plate-type fuel assembly in a cohesive way Z Yue, Y He, F Xiang, Y Wu, J Zhang, W Tian, G Su, S Qiu Nuclear Engineering and Design 413, 112548, 2023 | 3 | 2023 |
| Multi-physics coupling analysis on neutronics, thermal hydraulic and mechanics characteristics of a nuclear thermal propulsion reactor Z Duan, J Zhang, Y Wu, B Li, M Wang, Y He, W Tian, S Qiu, GH Su Nuclear Engineering and Design 399, 112042, 2022 | 3 | 2022 |
| Analysis of UO2-BeO Fuel Performance During Normal Conditions and RIA Y He, Y Wu, S Wang, B Qiu, GH Su International Conference on Nuclear Engineering 51531, V009T16A070, 2018 | 3 | 2018 |
| Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method Y Deng, H Liao, Y He, Y Yin, M Pellegrini, G Su, K Okamoto, Y Wu Nuclear Materials and Energy 36, 101463, 2023 | 2 | 2023 |
| Investigation of plate fuel performance under reactivity initiated accidents with developed multi-dimensional coupled method F Xiang, Y He, Y Wu, Y Niu, S Qiu, C Tang, K Wang, W Tian, G Su Journal of Nuclear Materials 583, 154537, 2023 | 2 | 2023 |
| Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code K Lu, H Yao, Y He, Y Wu, J Zhang, H Liao, GH Su, S Qiu Annals of Nuclear Energy 181, 109570, 2023 | 2 | 2023 |
Yangbin DengXi'an Jiaotong University在 stu.xjtu.edu.cn 的电子邮件经过验证
Yangbin DengXi'an Jiaotong University在 stu.xjtu.edu.cn 的电子邮件经过验证