scholarly journals Evaluation of irradiation hardening in ODS-Cu and non ODS-Cu by nanoindentation hardness test and micro-pillar compression test after self-ion irradiation

2021 ◽  
Vol 26 ◽  
pp. 100903
Author(s):  
Yuchen Liu ◽  
Sosuke Kondo ◽  
Hao Yu ◽  
Kiyohiro Yabuuchi ◽  
Ryuta Kasada
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.


2014 ◽  
Vol 89 (7-8) ◽  
pp. 1637-1641 ◽  
Author(s):  
Ryuta Kasada ◽  
Satoshi Konishi ◽  
Kiyohiro Yabuuchi ◽  
Shuhei Nogami ◽  
Masami Ando ◽  
...  

2018 ◽  
Vol 498 ◽  
pp. 274-281 ◽  
Author(s):  
A. Kareer ◽  
A. Prasitthipayong ◽  
D. Krumwiede ◽  
D.M. Collins ◽  
P. Hosemann ◽  
...  

2010 ◽  
Vol 654-656 ◽  
pp. 2915-2918 ◽  
Author(s):  
Yoshiyuki Takayama ◽  
Ryuta Kasada ◽  
Kiyohiro Yabuuchi ◽  
Akihiko Kimura ◽  
Dai Hamaguchi ◽  
...  

The effects of small amount (1 or 2 wt.%) of Ni additionson the irradiation hardening of the reduced-activation ferritic/martensitic steel, F82H, used as fusion reactor blanket structural materials were investigated by means of Fe-ion irradiation experimental test method and nano-indentation technique. The ion-irradiation hardening of Ni-added F82H is larger than that of the steel without Ni addition. The methodology to derive the irradiation hardening of ion-irradiated F82H steel was proposed from the results of hardness depth profile.


2007 ◽  
Vol 71 (12) ◽  
pp. 1107-1111 ◽  
Author(s):  
Masami Ando ◽  
Eiichi Wakai ◽  
Nariaki Ookubo ◽  
Hiroyuki Ogiwara ◽  
Tomotsugu Sawai ◽  
...  

2014 ◽  
Vol 941-944 ◽  
pp. 2202-2206
Author(s):  
Xian Zeng ◽  
Tomiko Yamaguchi ◽  
Yutaka Ida ◽  
Kazumasa Nishio

TiC0.3N0.7/TiN composite film was successfully formed on the surface of Ti-6Al-4V alloy by the treatment of YAG laser irradiation. In this paper an influence of laser output power on microstructure, chemical composition, element distribution and hardness, which were separately analyzed by scanning electron microscope (SEM), X-ray diffraction (XRD), electron probe micro-analyzer (EPMA) and nanoindentation hardness test, was investigated. Results showed that cross-section microstructure as-observed near the surface can be divided into three areas which were TiC0.3N0.7/TiN composite film, acicular structure and coarsening area, respectively. With increasing the output power, the thickness and the hardness of the TiC0.3N0.7/TiN layer were significantly improved.


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