| MATERIALS AND MATRIX COMPOSITES |
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| Hot Deformation Behavior of a Ni-Fe-Cr Based Superalloy for Advanced Ultra-supercritical Coal-fired Power Plants Application |
| HAN Liqing1, WU Yunsheng2,3, LIU Zhuang2, QIN Xuezhi2, WANG Changshuai2, ZHOU Lanzhang2, YU Hong1, CHEN Yajun4
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1 China Institute of Atomic Energy, Beijing 102413, China;
2 Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China;
3 School of Materials Science and Engineering, University of Science and Technology of China, Hefei 230026, China;
4 Department of Customer Development, Minmetals Development Co., LTD., Beijing 100044, China |
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Abstract The deformation behavior of a Ni-Fe-Cr based superalloy for 700 ℃ advanced ultra-supercritical (A-USC) power plant application was studied by the isothermal compression test at temperature range of 900—1 200 ℃ with strain rates of 0.01—10 s-1 on a Gleeble-1500 thermo-mechanical simulator. The results showed that the flow stress increased with the decreasing temperature and the increasing strain rate. The fraction of dynamic recrystallization decreased with the decreasing temperature and the increasing strain rate. However, when the strain rate was higher than 1 s-1, the fraction of dynamic recrystallization rose with the increasing strain rate due to the effect of adiabatic heating. The reasonable deformation temperature range of the alloy was 1 100—1 200 ℃, and the strain rate range was 0.01—0.3 s-1. The nucleation mechanism of dynamic recrystallization in the alloy was discontinuous dynamic recrystallization due to the existence of original grain boundaries bulging at high temperature and low strain rate. However, the dominant nucleation mechanism of dynamic recrystallization at low temperature and high strain rate turned into continuous dynamic recrystallization featured by sub-grains development within the original grains.
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Published: 12 March 2020
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| Fund:This work was financially supported by the National Key Research and Development Program of China (2017YFB0305204) and the National Natural Science Foundation of China (51871213). |
| About author:: Liqing Han, China Institute of Atomic Energy (CIAE), research associate. She received her Ph.D. degree in materials science and engineering from University of Science & Technology Beijing. She mainly engaged in reactor structural material design, research and development and evaluation. She has published more than 20 articles in important periodicals at home and abroad; Hong Yu, China Institute of Atomic Energy (CIAE), researcher. He received his Ph.D. degree in nuclear energy science and engineering from China Institute of Atomic Energy. He has published many articles in important periodicals at home and abroad. He mainly engaged in the integrated design of reactor. |
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