The Question of Saturation of Void Swelling in Fe-Cr-Ni Austenitic Alloys

2008 ◽  
pp. 767-767-11 ◽  
Author(s):  
FA Garner ◽  
CA Black
Keyword(s):  
Void Swelling ◽  
Austenitic Alloys

Void Swelling in Electron Irradiated High Purity Fe-Cr-Ni Austenitic Alloys

1978 ◽  
Vol 15 (9) ◽  
pp. 690-696 ◽  
Author(s):  
Akimichi HISHINUMA ◽  
Yoshio KATANO ◽  
Kensuke SHIRAISHI
Keyword(s):  
High Purity ◽  
Void Swelling ◽  
Austenitic Alloys

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.

Cascade damage effects on the swelling of irradiated materials

1975 ◽  
Vol 346 (1644) ◽  
pp. 81-102 ◽  
Keyword(s):  
Neutron Irradiation ◽  
Elevated Temperatures ◽  
Heavy Ion ◽  
Rate Theory ◽  
Void Swelling ◽  
Solution Treated ◽  
Continuous Generation ◽  
Volume Swelling ◽  
Physical Features ◽  
Cascade Damage

The homogeneous rate theory of void growth is extended to include the possibility of forming vacancy loops when the irradiation produces cascade damage. The analysis provides a basis for understanding and correlating the relative swelling generated during electron; heavy ion and fast neutron irradiation. In order to illustrate the physical features of the model it is applied in some detail to calculating the volume swelling in solution treated M316 stainless steel for which there is a considerable amount of experimental data. The results from these calculations serve to expose the sensitivity of void swelling to the scale on which interstitial loops are nucleated. They also highlight the particular difficulty arising from the continuous generation of transmutation gas in predicting swelling under neutron irradiation at elevated temperatures.

Helium embrittlement in Fe-Ni-Cr austenitic alloys and ferritic MA 956 alloy

1989 ◽  
Vol 169 ◽  
pp. 198-205 ◽  
Author(s):  
H. Shiraishi ◽  
N. Yamamoto ◽  
A. Hasegawa
Keyword(s):  
Austenitic Alloys ◽  
Helium Embrittlement

Point defect sink strengths and void-swelling

1976 ◽  
Vol 60 (3) ◽  
pp. 246-256 ◽  
Author(s):  
A.D. Brailsford ◽  
R. Bullough ◽  
M.R. Hayns
Keyword(s):  
Point Defect ◽  
Void Swelling

Damage structures in austenitic stainless steels during incubation period of void swelling

2009 ◽  
Vol 6 (11) ◽  
pp. 2333-2335 ◽  
Author(s):  
Toshimasa Yoshiie ◽  
Xingzhong Cao ◽  
Qiu Xu ◽  
Koichi Sato ◽  
T. D. Troev
Keyword(s):  
Incubation Period ◽  
Stainless Steels ◽  
Austenitic Stainless Steels ◽  
Void Swelling
Sign in / Sign up

Export Citation Format

Share Document