Irradiation induced dislocation loop and its influence on the hardening behavior of Fe–Cr alloys by an Fe ion irradiation

Author(s):  
Hyung-Ha Jin ◽  
Chansun Shin ◽  
Do Hyun Kim ◽  
Kyu Hwan Oh ◽  
Jun Hyun Kwon
2020 ◽  
Vol 5 (1) ◽  
pp. 1
Author(s):  
Ken-ichi Fukumoto ◽  
Yoshiki Kitamura ◽  
Shuichiro Miura ◽  
Kouji Fujita ◽  
Ryoya Ishigami ◽  
...  

A set of V–(4–8)Cr–(0–4)Ti alloys was fabricated to survey an optimum composition to reduce the radioactivity of V–Cr–Ti alloys. These alloys were subjected to nano-indenter tests before and after 2-MeV He-ion irradiation at 500 °C and 700 °C with 0.5 dpa at peak damage to investigate the effect of Cr and Ti addition and gas impurities for irradiation hardening behavior in V–Cr–Ti alloys. Cr and Ti addition to V–Cr–Ti alloys for solid–solution hardening remains small in the unirradiated V–(4–8)Cr–(0–4)Ti alloys. Irradiation hardening occurred for all V–Cr–Ti alloys. The V–4Cr–1Ti alloy shows the highest irradiation hardening among all V–Cr–Ti alloys and the gas impurity was enhanced to increase the irradiation hardening. These results may arise from the formation of Ti(CON) precipitate that was produced by He-ion irradiation. Irradiation hardening of V–Cr–1Ti did not depend significantly on Cr addition. Consequently, for irradiation hardening and void-swelling suppression, the optimum composition of V–Cr–Ti alloys for structural materials of fusion reactor engineering is proposed to be a highly purified V–(6–8)Cr–2Ti alloy.


MRS Advances ◽  
2016 ◽  
Vol 1 (42) ◽  
pp. 2887-2892
Author(s):  
Brittany Muntifering ◽  
Jianmin Qu ◽  
Khalid Hattar

ABSTRACTThe formation and stability of radiation-induced defects in structural materials in reactor environments significantly effects their integrity and performance. Hydrogen, which may be present in significant quantities in future reactors, may play an important role in defect evolution. To characterize the effect of hydrogen on cascade damage evolution, in-situ TEM self-ion irradiation and deuterium implantation was performed, both sequentially and concurrently, on nickel. This paper presents preliminary results characterizing dislocation loop formation and evolution during room temperature deuterium implantation and self-ion irradiation and the consequence of the sequence of irradiation. Hydrogen isotope implantation at room temperature appears to have little or no effect on the final dislocation loop structures that result from self-ion irradiation, regardless of the sequence of irradiation. Tilting experiments emphasize the importance of precise two-beam conditions for characterizing defect size and structure.


2021 ◽  
pp. 153390
Author(s):  
Caleb Clement ◽  
Yangyang Zhao ◽  
Patrick Warren ◽  
Xiang Liu ◽  
Sichuang Xue ◽  
...  

2019 ◽  
Vol 125 (8) ◽  
pp. 085109
Author(s):  
Qiang Wang ◽  
Levente Balogh ◽  
Qingshan Dong ◽  
Ning Guo ◽  
Zhongwen Yao ◽  
...  

2021 ◽  
pp. 153489
Author(s):  
Phongsakorn Prak Tom ◽  
Kenta Murakami ◽  
Luu Vu Nhut ◽  
Nguyen Ba Vu Chinh ◽  
Liang Chen

2012 ◽  
Vol 423 (1-3) ◽  
pp. 170-182 ◽  
Author(s):  
R.M. Hengstler-Eger ◽  
P. Baldo ◽  
L. Beck ◽  
J. Dorner ◽  
K. Ertl ◽  
...  

1998 ◽  
Vol 258-263 ◽  
pp. 873-878 ◽  
Author(s):  
H Iwakiri ◽  
H Wakimoto ◽  
H Watanabe ◽  
N Yoshida

2010 ◽  
Vol 400 (1) ◽  
pp. 56-63 ◽  
Author(s):  
A. Etienne ◽  
M. Hernández-Mayoral ◽  
C. Genevois ◽  
B. Radiguet ◽  
P. Pareige

1994 ◽  
Vol 35 (1) ◽  
pp. 7-13
Author(s):  
Naoto Shigenaka ◽  
Tsuneyuki Hashimoto ◽  
Motomasa Fuse

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