Energy Materials Group
Brief Introduction
The research activity of radiation damage of reactor materials in IMP was launched in 1980s to meet the demand of the R&D of structural materials for the Fission/Fusion Hybrid Reactor program in China. The Energy Materials Group, since her foundation in 2011, has been dedicated to pushing forward the radiation damage research by utilizing high-energy ion accelerators in IMP.
Thanks to the fast development of the nuclear energy field in China, the group joined several national projects including the National Magnetic Confinement Program, the Chinese Prototype Fast Reactor Program, and the China Nuclear Reactor Life Extension Program. The group was also sponsored by the National Science Foundation of China.
Our research activity covers fundamental studies on the radiation damage evolution in advanced nuclear reactor materials including ODS ferritic steels and SiCf/SiC composites, and evaluation of key materials for Gen III and Gen IV reactors. A specialized irradiation terminal was setup at HIRFL for material irradiation.
Now the group has 8 staffs, 1 postdoc researchers and 4 postgraduate students. We sincerely welcome industrious young people to join us.
Research activities cover fundamental studies on the radiation damage evolution in advanced nuclear reactor materials, including ODS ferritic steels and SiCf/SiC composites, and evaluation of key materials for Gen III and Gen IV reactors. A specialized irradiation terminal was set up at HIRFL for material irradiation.
Now the group has 7 staffs, 2 postdoc researchers and 3 postgraduate students. We sincerely welcome industrious young people to join us.
Research Fields
The Energy Materials Group has been dedicated to pushing forward the radiation damage research of advanced nuclear reactors. It includes the setup of facilities and methods for the evaluation of material performance under intensive irradiation condition, the identification of mechanisms underlying particle irradiation, the modeling of damage evolution. The ongoing studies in our group are listed as follows.
1. Radiation embrittlement of structural materials candidate to fast and fusion reactors;
2. High throughput technology for the evaluation of life extension of RPV steels;
3. Mechanisms underlying radiation response of the FeCrAl-base ODS ferritic steel and SiCf/SiC composites
Achievements
About 40 papers were published in refereed journals (in English) while 4 patents were granted since 2011. Papers representing our research progress are listed as follows in two categories.
1. Structural characterization and radiation embrittlement of ODS ferritic steels
C.H. Zhang, A. Kimura, S. Kasada, J. Jang, H. Kishimoto, Y.T. Yang, Characterization of the oxide particles in Al-added high-Cr ODS ferritic steels, Journal of Nuclear Materials 417(2011)221;
C.H. Zhang, Y.T. Yang, Y. Song, J. Chen, L.Q. Zhang, J. Jang, A. Kimura, Irradiation response of ODS ferritic steels to high-energy Ne ions at HIRFL, Journal of Nuclear Materials 455(2014)61;
Z.N. Ding, C.H. Zhang, Y.T. Yang, Y. Song, A. Kimura, J. Jang, Hardening of ODS ferritic steels under irradiation with high-energy heavy ions, Journal of Nuclear Materials 493 (2017)53;
Yuguang Chen, Chonghong Zhang, Zhaonan Ding, XianLong Zhang, Yitao Yang, Yin Song, Akihiko Kimura, Annealing behavior of hardening and ductility loss of a 16Cr-4Al ODS ferritic steel irradiated with high energy Ne ions, Journal of Nuclear Materials 531 (2020) 152030；
Xuxiao Han, Chonghong Zhang, Mengke Niu, Zhaonan Ding, Jinsung Jang, Tieshan Wang, Akihiko Kimura, A comparison study of change in hardness and microstructures of a Zr-added FeCrAl ODS steel irradiated with heavy ions, Materials Science & Engineering A 531 (2020) 152014.
2. Methodology for evaluation of irradiation response of materials by heavy-ion irradiation
Yitao Yang, Chonghong Zhang, Zhaonan Ding, Changhao Su, Tingxin Yan, Yuguang Chen, A correlation between micro-and nano-indentation on materials irradiated by high-energy heavy ions, Journal of Nuclear Materials 498(2018)129;
Xianlong Zhang et al, Quantifification of the constitutive relationship of high-energy heavy ion irradiated SS316L using the small punch test, Journal of Nuclear Materials 531 (2020) 152014.
3. Correlation of radiation damage in Fe-base alloys by different particles
Jianyang Li, Chonghong Zhanga, Yitao Yang, Tieshan Wang, Ignacio Martin-Bragado, Irradiation dose-rate effect in Fe-C system: An Object Kinetic Monte Carlo simulation, Journal of Nuclear Materials 561 (2022) 153529.
Photos
Contact
Prof. ZHANG Chonghong Dr. Yitao Yang
Tel: 86-931-4969036
Email: c.h.zhang@impcas.ac.cn; yangyt@impcas.ac.cn
Mailing Address: 509 Nanchang Road, Lanzhou 730000, China
Copyright © Institute of Modern Physics, Chinese Academy of SciencesAddress：509 Nanchang Rd., Lanzhou 730000, ChinaEmail: office@impcas.ac.cn
陇ICP备2023003351号-1 
甘公网安备 62010202000713号
