He+离子辐照后Hastelloy N合金的耐腐蚀性研究

doi:10.11889/j.0253-3219.2014.hjs.37.050601

Nuclear Techniques ›› 2014, Vol. 37 ›› Issue (05): 50601-050601.doi: 10.11889/j.0253-3219.2014.hjs.37.050601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles Next Articles

Investigation on corrosion resistance of Hastelloy N alloy after He+ ion irradiation

LIN Jianbo1,2 LI Aiguo1 HE Shangming1 YU Xiaohan1

1(Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China) 2(University of Chinese Academy of Sciences, Beijing 100049, China)

Received:2014-02-20 Revised:2014-03-31 Online:2014-05-10 Published:2014-05-08
Supported by:
;NSFC

Abstract

Abstract:

Background: The invalidation problems of irradiated Hastelloy N alloy caused by high temperature, intense irradiation and severe corrosion are the key factors to the service life of structural materials of molten salt reactor (MSR). Purpose: The aim is to investigate the effect of absorbed dose on the corrosion resistance of Hastelloy N alloy. Methods: Hastelloy N alloy was irradiated by 4.5-MeV He+ ions, and the absorbed doses were 0 He+?cm?2, 1×1015 He+?cm?2, 5×1015 He+?cm?2 and 1×1016 He+?cm?2 respectively. The virgin and irradiated specimens were immersed into molten fluoride salts at 700 oC for 300 h. Then the corroded specimens were imaged by scanning electron microscopy and analyzed by synchrotron radiation microbeam X-ray fluorescence (?-XRF). Results: The weight-loss results showed that the corrosion generally correlated with the absorbed dose of the alloy. The ?-XRF results indicated that the corrosion was mainly due to the dealloying of alloying element Cr in the matrix. Conclusion: The density of dislocations of Hastelloy N alloy increased with the absorbed dose, which acted as quick paths for Cr element diffusion, and the diffusion of element Cr out of matrix became easier. Finally became weak of the corrosion resistance of Hatelloy N alloy.

Key words: Hastelloy N alloy, Ion irradiation, Microbeam X-ray fluorescence alalysis (u-XRF), Thorium Molten Salt Reactor (TMSR), Stopping and Range of Ions in Matter (SRIM), Molten fluoride salts, Corrosion

LIN Jianbo, LI Aiguo, HE Shangming, YU Xiaohan. Investigation on corrosion resistance of Hastelloy N alloy after He+ ion irradiation[J].Nuclear Techniques, 2014, 37(05): 50601-050601.

[1]	Guanhong LEI, Sida YANG, Renduo LIU, Jianjian LI, Qing HUANG, Cheng LI, Hefei HUANG, Long YAN. The effect of He bubbles on the corrosion properties of nickel-based alloy in molten salt environment [J]. Nuclear Science and Techniques, 2019, 42(4): 40602-040602.
[2]	Xiang ZHANG, Xiaoqiang PAN, Chaohong LIU, Jing YANG, Qiang ZENG. Study on compatibility between U-Zr alloy fuel with lead, bismuth alloy [J]. Nuclear Science and Techniques, 2019, 42(3): 30603-030603.
[3]	DING Siyuan, WANG Xue, WANG Mao, SHEN Wenhao, LIU Feng, WANG Yugang. SAXS measurements of polymeric sub-nanometer pores [J]. Nuclear Techniques, 2018, 41(12): 120102-120102.
[4]	LIU Shuting, SU Tao, ZHANG Peng, LIU Hongtao. Development of high-temperature in situ infrared absorption instrument used for molten fluoride salts [J]. Nuclear Techniques, 2017, 40(7): 70604-070604.
[5]	ZENG Qifeng, ZHU Libing, YUAN Gaihuan, WANG Lian, LIU Jiazheng, GAO Bo. Study on new zirconium alloys for CAP1400 fuel assembly [J]. Nuclear Techniques, 2017, 40(3): 30602-030602.
[6]	LUO Sheng, YANG Liang, GUO Guqing, GE Tao. Enhanced mechanical properties and corrosion resistance of Zr-based amorphous/crystalline nuclear material [J]. Nuclear Techniques, 2016, 39(2): 20501-020501.
[7]	LI Lu, ZHANG Jingyu, GUO Qingyang, CHEN Yixue. Calculation and analysis of activation products source term in water-cooled fusion reactor primary circuit [J]. Nuclear Techniques, 2016, 39(11): 110603-110603.
[8]	QIU Jie, ZOU Yang, LI Zhijun, XU Hongjie. Corrosion behaviors of nickel-based high temperature alloys in molten FLiNaK salt [J]. Nuclear Techniques, 2015, 38(7): 70601-070601.
[9]	WANG Feifei, WANG Hailing, YU Haiying. Research on three dimensional diffusion equation in the reactor calculation application based on GPU [J]. Nuclear Techniques, 2015, 38(4): 40502-040502.
[10]	LIU Ke, XU Liang, LIU Zhe, LONG Shilei, CAO Lingling, BAO Liangman, LI Xiaolin, ZHANG Guilin, LI Yan. Impact of temperature on the molten salt corrosion of Hastelloy-N alloys [J]. Nuclear Techniques, 2015, 38(2): 20602-020602.
[11]	LI Ling, YU Guojun, ZHOU Xingtai. Corrosion behaviour of Ti3SiC2 and Ti3AlC2 with LiF-NaF-KF molten salt [J]. Nuclear Techniques, 2014, 37(06): 60602-060602.
[12]	YANG Jingyi, YAN Long, HUAI Ping. Surface structure investigation of C/C composites by Ar ion irradiation [J]. Nuclear Techniques, 2014, 37(05): 50202-050202.
[13]	HUANG Can, YANG Kang, MA Mingwang, HAI Yang, ZHANG Zengyan, ZHAO Hongwei, ZHU Zhiyong. Defect effects on THz wave emission induced by ion irradiation [J]. Nuclear Techniques, 2014, 37(04): 40501-040501.

Investigation on corrosion resistance of Hastelloy N alloy after He+ ion irradiation

PDF (PC)

Like

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 13

Metrics

Comments

Recommended 10