Supervisor of Doctorate Candidates
Supervisor of Master's Candidates
Name (Simplified Chinese): Sun Fei
Name (English): Sun Fei
Name (Pinyin): sunfei
E-Mail:
School/Department: 金属材料工程系
Education Level: Postgraduate (Doctoral)
Business Address: 屯溪路校区材料楼N403
Degree: Doctoral Degree in Engineering
Professional Title: Professor
Alma Mater: 华中科技大学
Supervisor of Doctorate Candidates
Supervisor of Master's Candidates
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# 2025
1.F. Sun, Q. Liu, B. Xu, X.C. Li, J. Zhu, D. Zhu, H.S. Zhou*, H. Zong, L.M. Luo, Y. Oya, Y. Wu, Trapping and de-trapping behavior of hydrogen isotopes in <100> interstitial dislocation loops of tungsten, Nuclear Fusion, 65 (2025) 076010.[Link](JCR 一区，顶刊)
2.Q. Liu, F. Sun*, J. Zhu, H.S. Zhou, H. Zong, Z. Yang, H.B. Zhou, Y. Oya, Y. Wu, A novel mechanism and model of hydrogen isotope exchange in vacancy considering nuclear quantum effects, Nuclear Fusion, 65 (2025) 016047.[Link](JCR 一区，顶刊)
3.T. Li, X. Pang, Y. Wang, X. Ding*, F. Sun*, H. Zong*, J. Sun, Origin of exceptional structural stability in refractory amorphous high-entropy alloys under ion irradiation, Acta Materialia, 292 (2025) 121078.[Link](JCR 一区，顶刊)
4.B. Fan, F. Sun*, Q. Liu, X.C. Li, J. Zhu, K.Y. Lu, H.L. Yang, H.S. Zhou, R. Ding, L.M. Luo, Y. Oya, Y. Wu, Effect of the transmutation element rhenium on the retention, desorption, and diffusion behavior of hydrogen isotopes in tungsten, Journal of Nuclear Materials, 607 (2025) 155693.[Link](JCR 一区)
5.F. Sun*, X. Lin, Y. Huang, J. Zhu, L. Cheng, Y. Zhang*, H.S. Zhou, L.M. Luo, Y. Oya, Y. Wu, A vacancy dynamic evolution model based on rate theory and its influence on hydrogen isotope retention behavior, Journal of Nuclear Materials, 607 (2025) 155676.[Link](JCR 一区)
6.S. Gu, Q. Qi*, F. Sun*, Y. Zhang, Y. Oya, H.S. Zhou, G.N. Luo, Tritium release performance of neutron-irradiated core–shell Li2TiO3-Li4SiO4 pebbles, Nuclear Materials and Energy, 43 (2025) 101917.[Link](JCR 一区)
7.Y. Hoshino*, F. Sun, M. I. Kobayashi, T. Toyama, R. Kolasinski, C. N. Taylor, M. Shimada, Y. Hatano, Y. Oya, Effects of neutron irradiation on hydrogen isotope permeation on W-Re, Fusion Engineering and Design, 211 (2025) 114769.[Link](JCR 一区)
8.Y.F. Wang, G.F. Li, J.X. Chen, L.M. Luo*, Y.Q. Qin, F. Sun*, D. Dong, Y.C. Wu, Deformation behaviors and microstructure evolution of sintered W-10Re alloy under different conditions, International Journal of Refractory Metals and Hard Materials, 130 (2025) 107158.[Link](JCR 一区)
9.Y.F. Wang, J.X. Chen, L.M. Luo*, Y.Q. Qin*, F. Sun, D. Dong, Y.C. Wu, Evolution of microstructure and mechanical properties of warm-rolled W-10Re alloy during annealing at 1500 °C, International Journal of Refractory Metals and Hard Materials, 127 (2025) 106968.[Link](JCR 一区)
# 2024
10.F. Sun, C. Hao, D.Y. Chen, H.S. Zhou*, Y. Oya, J.P. Zhu, J. Tang, H. Zong, L.M. Luo*, Y.C. Wu, Mechanism of hydrogen isotope exchange for tritium removal in plasma-facing materials: a multi-scale investigation, Nuclear Fusion, 64 (2024) 046011.[Link](JCR 一区，顶刊)
11.Y.F. Wang, Z.H. Chen, J.X. Chen, L.M. Luo*, F. Sun, Y.C. Wu*, High strength and tackling structural relaxation by sub-grains synergistic deformation in W-Re alloy, Materials Science and Engineering: A, 914 (2024) 147160.[Link](JCR 一区)
12.J. Zhu, X. Ye, C.A. Chen*, F. Sun, W. Jin, X. Liu, Modeling the Co-permeation of Hydrogen Isotopes through Metals in All Rate-Limited Regimes, Journal of Nuclear Materials, 601 (2024) 155290.[Link](JCR 一区)
13.F. Sun, D.Y. Chen, Q.H. Liu, J.P. Zhu, X.C. Li*, H.S. Zhou, Y. Oya, L.M. Luo, Y.C. Wu, Competitive barrier and trapping effects of helium bubbles on hydrogen isotopes migration behavior in tungsten, Journal of Nuclear Materials, 599 (2024) 155197.[Link](JCR 一区)
14.B.C. Xu, Y.W. Li, Y. Mai, Z. Li, W. Wu, X.C. Li*, X.D. Pan, F. Sun, H.S. Zhou*, G.N. Luo, Synergistic influence of dislocations and helium cluster on hydrogen atom in tungsten, Journal of Nuclear Materials, 596 (2024) 155110.[Link](JCR 一区)
15.Y.J. Huang, C. Hao, Q.H. Liu, J.P. Zhu, F. Sun*, Y. Oya, Y.C. Wu, Influence of helium bubbles location on hydrogen isotope retention and exchange behavior in plasma-facing materials: a numerical simulation investigation, Nuclear Materials and Energy, 38 (2024) 101596.[Link](JCR 一区)
# 2023
16.Y. Oya*, N. Inozume, Y. Hoshino, N. Yoshida, T. Hinoki, K. Yabuuchi, Y. Hatano, Q. Zhou, F. Sun, R. Kolasinski, C.N. Taylor, M. Shimada, Thermal annealing effect on D retention for damaged W-10%Re alloy, Fusion Engineering and Design, 196 (2023) 113981.[Link](JCR 一区)
17.F. Sun*, D.Y. Chen, C. Hao, Y. Oya, J.P. Zhu, D.D. Li, L.M. Luo, Y.C. Wu, Estimation of different calculation models for evaluating heavy ion-induced damage in plasma facing materials, Fusion Engineering and Design, 194 (2023) 113910.[Link](JCR 一区)
18.J. Zhou, H. Chen, R. Zhou, Y.W. You, F. Sun, D. Li*, The formation and migration of point defects and the thermodynamic behavior of TiD2 by first-principles calculations, Journal of Nuclear Materials, 583 (2023) 154552.[Link](JCR 一区)
19.Y. Oya*, K. Ashizawa, F. Sun, S. Hirata, N. Ashikawa, Y. Someya, Y. Hatano, R. Kolasinski, C. N. Taylor, M. Shimada, Effect of He seeding on hydrogen isotope permeation in tungsten by H-D mixed plasma exposure, Fusion Engineering and Design, 194 (2023) 113722.[Link](JCR 一区)
20.Q. Zhou*, F. Sun, S. Hirata, S. Li, Y. Li, Y. Oya*, Effect of neutron dose on the tritium release behavior of Li2TiO3–0.5Li4SiO4 biphasic ceramic, International Journal of Hydrogen Energy, 48 (2023) 4363-4370.[Link](JCR 一区)
# 2022
21.S. Hirata*, K. Ashizawa, F. Sun, Y. Feng, X. Wang, H. Wang, M. Kobayashi, A. Taguchi, Y. Oya, Tritium recovery behavior for tritium breeder Li4SiO4-Li2TiO3 biphasic material, Journal of Nuclear Materials, 567 (2022) 153838.[Link](JCR 一区)
22.A. Koike*, S. Yamazaki, T. Wada, F. Sun, N. Yoshida, K. Hanada, Y. Oya, Evaluation of hydrogen retention behavior for damaged tungsten exposed to hydrogen plasma at QUEST with high temperature wall, Fusion Engineering and Design, 176 (2022) 113020.[Link](JCR 一区)
# 2021
23.T. Wada*, A. Koike, S. Yamazaki, K. Ashizawa, F. Sun, Y. Hatano, H. Shimoyachi, T. Kenmotsu, T. Ikka, Y. Oya*, Protective behavior of tea catechins against DNA double strand breaks produced by radiations with different linear energy transfer, Fusion Engineering and Design, 172 (2021) 112700.[Link](JCR 一区)
24.Q. Qi, M. Zhao, F. Sun, Y. Zhang, S. Gu, B. Ji, H. Zhou*, Y. Oya, S. Liu, G. Luo, Investigation on effects of tritium release behavior in Li4SiO4 pebbles, Nuclear Materials and Energy, 28 (2021) 101036.[Link](JCR 一区)
25.A. Koike*, M. Nakata, S. Yamazaki, T. Wada, F. Sun, M. Zhao, N. Yoshida, K. Hanada, Y. Oya, Evaluation of hydrogen retention behavior in tungsten exposed to hydrogen plasma in QUEST , Nuclear Materials and Energy, 26 (2021) 100856.[Link](JCR 一区)
# 2020
26.F. Sun*, X.C. Li, L. Zhang, M. Nakata, M. Zhao, T. Wada, S. Yamazaki, A. Koike, Y. Oya, Modeling and simulation for surface helium effect on hydrogen isotopes diffusion and trapping/detrapping behavior in plasma facing materials, Journal of Nuclear Materials, 537 (2020) 152227.[Link](JCR 一区)
27.F. Sun*, M. Nakata, S.E. Lee, M. Zhao, T. Wada, S. Yamazaki, A. Koike, S. Kondo, T. Hinoki, M. Hara, Y. Oya, Synergistic effects of high energy helium irradiation and damage introduction at high temperature on hydrogen isotope retention in plasma facing materials, Journal of Nuclear Materials, 533 (2020) 152122.[Link](JCR 一区)
28.Y. Oya*, A. Togari, M. Nakata, A. Koike, T. Wada. S. Yamazaki, M. Zhao, F. Sun, M. Yajima, S. Masuzaki, Hydrogen isotope exchange at the surface of C-W mixed material layer on tungsten by gas exposure, Fusion Engineering and Design, 157 (2020) 111633.[Link](JCR 一区)
29.Y. Oya*, F. Sun, Y. Yamauchi, Y. Nobuta, M. Shimada, C.N. Taylor, W.R. Wampled, M. Nakata, L.M. Garrisone, Y. Hatano, D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation, Journal of Nuclear Materials, 539 (2020) 152323.[Link](JCR 一区)
30.Y. Oya*, S. Masuzaki, M. Tokitani, M. Nakata, F. Sun, M. Oyaidzu, K. Isobe, N. Asakura, T. Otska, A. Widdowson, J. Likonen, M. Rubel, JET Contributors, Comparison of Hydrogen Isotope Retention in Divertor Tiles of JET with the ITER-Like Wall Following Campaigns in 2011–2012 and 2015–2016, Fusion Science and Technology, 76 (2020) 439-445.[Link]
31.M. Zhao*, S. Yamazaki, T. Wada, A. Koike, F. Sun, N. Ashikawa, Y. Someya, T. Mieno, Y. Oya, Deuterium recombination coefficient on tungsten surface determined by plasma driven permeation, Fusion Engineering and Design, 160 (2020) 111853.[Link](JCR 一区)
32.Q. Zhou*, A. Togari, M. Nakata, M. Zhao, F. Sun, M. Yajima, M. Tokitani, S. Masuzaki, N. Yoshida, M. Hara, Y. Hatano, Y. Oya, Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H2+ at high temperature, International Journal of Hydrogen Energy, 45 (2020) 9959-9968.[Link](JCR 一区)
33.M. Zhao*, M. Nakata, F. Sun, Y. Hatano, Y. Someya, K. Tobita, Y. Oya, Deuterium Permeation Behavior in Fe Ion Damaged Tungsten Studied by Gas-Driven Permeation Method, Fusion Science and Technology, 76 (2020) 246-251.[Link]
# 2019
34.F. Sun, B. Li, C. Cai, Q. Cai*, Effects of TiN nanoparticles on hot deformation behavior of ultra-fine grained Al2024-TiN nanocomposites prepared by spark plasma sintering, Mechanics of Materials, 138 (2019) 103152.[Link](JCR 一区)
35.N. Wang, F. Sun*, Q. Zhou, D.M. Liao, Y.W. Yan, First-principles study on hydrogen diffusion mechanism of α-Al2O3/Ti2O3 interface, Fusion Engineering and Design, 142 (2019) 40-44.[Link](JCR 一区)
36.F. Sun, D.Q. Zhang, L. Cheng, P. Zheng, D.M. Liao, B. Zhu, Microstructure evolution modeling and simulation for dynamic recrystallization of Cr12MoV die steel during hot compression based on real metallographic image, Metals and Materials International, 25 (2019) 966-981.[Link](JCR 一区)
37.Z.H. Teng, D.M. Liao, S.C. Wu, F. Sun, T. Chen, Z.B. Zhang, An adaptively refined XFEM for the dynamic fracture problems with micro-defects, Theoretical and Applied Fracture Mechanics, 108 (2019) 102255.[Link](JCR 一区)
38.Q. Zhou*, A. Togari, M. Nakata, M. Zhao, F. Sun, Q. Xu, Y. Oya, Release kinetics of tritium generation in neutron irradiated biphasic Li2TiO3–Li4SiO4 ceramic breeder, Journal of Nuclear Materials, 522 (2019) 286-293.[Link](JCR 一区)
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(Updated at Jun. 2025)
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