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Multi-scale modeling of radiation damage in FeCr alloy

## Multi-scale modeling of radiation damage in FeCr alloy

He Xin-Fu, Yang Wen, Fan Sheng
• #### Abstract

Since irradiation experiments of ferritic/martensitic （F/M） FeCr alloys show that F/M steels undergo much less swelling than austenitic steels during neutron or charged particle irradiation，in addition, it is well-known that high chromium content of F/M alloys provide good resistance against corrosion, they are considered as one of the most attractive candidate materials for future nuclear facilities, such as Fusion Reactor, ADS and generation Ⅳ reactors. Although irradiation experiments can not be replaced by modeling, a purely experimental approach to understanding the effects of irradiation is also not practicable, so in recent years substantial progress has been made in the field of multi-scale modeling of radiation damage in F/M FeCr alloys. The present paper is a review of methods used and results achieved within the last couple of years, and some suggestions are put forward for the further improvements.

• Funds:

#### Cited By

•  [1] Cui Zhen-Guo, Gou Cheng-Jun, Hou Qing, Mao Li, Zhou Xiao-Song. Computer simulation of radiation damage caused by low energy neutron in zirconium. Acta Physica Sinica, 2013, 62(15): 156105. doi: 10.7498/aps.62.156105 [2] Zhu Yong, Li Bao-Hua, Xie Guo-Feng. Investigation of proton irradiation damage in BaTiO3 thin film by computer simulation. Acta Physica Sinica, 2012, 61(4): 046103. doi: 10.7498/aps.61.046103 [3] Jiang Shao-Ning, Wan Fa-Rong, Long Yi, Liu Chuan-Xin, Zhan Qian, Ohnuki Somei. Effects of helium and deuterium on irradiation damage in pure iron. Acta Physica Sinica, 2013, 62(16): 166801. doi: 10.7498/aps.62.166801 [4] Shao Yu-Fei, Wang Shao-Qing. Quasicontinuum simulation of crack propagation in nanocrystalline Ni. Acta Physica Sinica, 2010, 59(10): 7258-7265. doi: 10.7498/aps.59.7258 [5] Wang Jun, Zhang Bao-Ling, Zhou Yu-Lu, Hou Qing. Molecular dynamics simulation of helium behavior in tungsten matrix. Acta Physica Sinica, 2011, 60(10): 106601. doi: 10.7498/aps.60.106601 [6] Liang Jin-Jie, Gao Ning, Li Yu-Hong. Surface effect on \begin{document}${\langle 100 \rangle }$\end{document} interstitial dislocation loop in iron. Acta Physica Sinica, 2020, 69(3): 036101. doi: 10.7498/aps.69.20191379 [7] Gao Yun-Liang, Zhu Yuan-Jiang, Li Jin-Ping. First-principle study of initial irradiation damage in aluminum. Acta Physica Sinica, 2017, 66(5): 057104. doi: 10.7498/aps.66.057104 [8] Lan Mu-Jie, Wu Yi-Yong, Yue Long, Xiao Jing-Dong, Yang De-Zhuang, He Shi-Yu, Hu Jian-Min, Zhang Zhong-Wei, Wang Xun-Chun, Qian Yong, Chen Ming-Bo. Radiation damage of space GaAs/Ge solar cells evaluated by displacement damage dose. Acta Physica Sinica, 2011, 60(9): 098110. doi: 10.7498/aps.60.098110 [9] Qi Jia-Hong, Hu Jian-Min, Sheng Yan-Hui, Wu Yi-Yong, Xu Jian-Wen, Wang Yue-Yuan, YANG Xiao-Ming, Zhang Zi-Rui, Zhou Yang. Carrier transport mechanism of GaAs/Ge solar cells under electrons irradiation. Acta Physica Sinica, 2015, 64(10): 108802. doi: 10.7498/aps.64.108802 [10] Chang Xiao-Yang, Yao Shun, Zhang Qi-Ling, Zhang Yang, Wu Bo, Zhan Rong, Yang Cui-Bai, Wang Zhi-Yong. Anti-radiation of space triple-junction solar cell based on distributed Bragg reflector structure. Acta Physica Sinica, 2016, 65(10): 108801. doi: 10.7498/aps.65.108801
•  Citation:
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• Abstract views:  3855
• Cited By: 0
##### Publishing process
• Received Date:  07 January 2009
• Accepted Date:  18 March 2009
• Published Online:  20 December 2009

## Multi-scale modeling of radiation damage in FeCr alloy

• 1. 中国原子能科学研究院，北京 102413

Abstract: Since irradiation experiments of ferritic/martensitic （F/M） FeCr alloys show that F/M steels undergo much less swelling than austenitic steels during neutron or charged particle irradiation，in addition, it is well-known that high chromium content of F/M alloys provide good resistance against corrosion, they are considered as one of the most attractive candidate materials for future nuclear facilities, such as Fusion Reactor, ADS and generation Ⅳ reactors. Although irradiation experiments can not be replaced by modeling, a purely experimental approach to understanding the effects of irradiation is also not practicable, so in recent years substantial progress has been made in the field of multi-scale modeling of radiation damage in F/M FeCr alloys. The present paper is a review of methods used and results achieved within the last couple of years, and some suggestions are put forward for the further improvements.

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