Ar ion irradiation hardening of high-Cr ferritic/martensitic steels at 700 °C

2016 ◽  
Vol 22 (2) ◽  
pp. 181-186 ◽  
Author(s):  
Yinzhong Shen ◽  
Jun Zhu ◽  
Xi Huang
Keyword(s):  
Ion Irradiation ◽  
Martensitic Steels ◽  
Irradiation Hardening

scholarly journals Irradiation Hardening Behavior of He-Irradiated V–Cr–Ti Alloys with Low Ti Addition

2020 ◽  
Vol 5 (1) ◽  
pp. 1
Author(s):  
Ken-ichi Fukumoto ◽  
Yoshiki Kitamura ◽  
Shuichiro Miura ◽  
Kouji Fujita ◽  
Ryoya Ishigami ◽  
...  
Keyword(s):  
Ion Irradiation ◽  
Optimum Composition ◽  
Solid Solution Hardening ◽  
Irradiation Hardening ◽  
Hardening Behavior ◽  
Ti Alloys ◽  
Void Swelling ◽  
Before And After ◽  
Cr Addition ◽  
Ti Addition

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.

Irradiation hardening of reduced activation martensitic steels

1996 ◽  
Vol 233-237 ◽  
pp. 319-325 ◽  
Author(s):  
A. Kimura ◽  
T. Morimura ◽  
M. Narui ◽  
H. Matsui
Keyword(s):  
Martensitic Steels ◽  
Irradiation Hardening

Evaluation of Irradiation Hardening of Fe-Ion Irradiated F82H by Nano-Indentation Techniques

2010 ◽  
Vol 654-656 ◽  
pp. 2915-2918 ◽  
Author(s):  
Yoshiyuki Takayama ◽  
Ryuta Kasada ◽  
Kiyohiro Yabuuchi ◽  
Akihiko Kimura ◽  
Dai Hamaguchi ◽  
...  
Keyword(s):  
Experimental Test ◽  
Fusion Reactor ◽  
Martensitic Steel ◽  
Ion Irradiation ◽  
Test Method ◽  
Irradiation Hardening ◽  
Nano Indentation ◽  
Ni Addition ◽  
Fusion Reactor Blanket ◽  
Hardness Depth

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.

scholarly journals Extra-Irradiation Hardening of Reduced Activation Ferritic/Martensitic Steel by Multi-Ion Irradiation

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

Microstructure and Mechanical Properties of n-Irradiated Fe-Cr Model Alloys

2006 ◽  
Vol 981 ◽  
Author(s):  
Milena Matijasevic ◽  
Abderrahim Al Mazouzi
Keyword(s):  
Mechanical Stability ◽  
Tensile Tests ◽  
High Energy ◽  
Mechanical Tests ◽  
Test Results ◽  
Martensitic Steels ◽  
Irradiation Hardening ◽  
Cr Concentration ◽  
Accelerator Driven Systems

AbstractHigh chromium ( 9-12 wt %) ferritic/martensitic steels are candidate structural materials for future fusion reactors and other advanced systems such as accelerator driven systems ADS). Their use for these applications requires a careful assessment of their mechanical stability under high energy neutron irradiation and in aggressive environments. In particular, the Cr concentration has been shown to be a key parameter to be optimized in order to guarantee the best corrosion and swelling resistance, together with the least embrittlement.In this work, the characterization of the neutron irradiated Fe-Cr model alloys with different Cr % with respect to microstructure and mechanical tests will be presented. The behavior of Fe-Cr alloys have been studied using tensile tests at different temperature range ( from -160°C to 300°C). Irradiation-induced microstructure changes have been studied by TEM for two different irradiation doses at 300°. The density and the size distribution of the defects induced have been determined. The tensile test results indicate that Cr content affects the hardening behavior of Fe-Cr binary alloys. Hardening mechanisms are discussed in terms of Orowan type of approach by correlating TEM data to the measured irradiation hardening.

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