Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation

2017 ◽  
pp. 669-680 ◽  
Author(s):  
C. Sun ◽  
L. Malerba ◽  
M. J. Konstantinovic ◽  
F. A. Garner ◽  
S. A. Maloy
Keyword(s):  
Stainless Steels ◽  
Ion Irradiation ◽  
Void Swelling

A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation

2021 ◽  
pp. 152946
Author(s):  
Li Jiang ◽  
Miao Song ◽  
Liuqing Yang ◽  
Jingfan Yang ◽  
Donghai Du ◽  
...  
Keyword(s):  
Stainless Steels ◽  
Ion Irradiation ◽  
Comparison Study ◽  
Void Swelling ◽  
Cold Worked

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.

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

scholarly journals The Effect of Internal Free Surfaces on Void Swelling of Irradiated Pure Iron Containing Subsurface Trenches

Crystals ◽  
2019 ◽  
Vol 9 (5) ◽  
pp. 252
Author(s):  
Tianyao Wang ◽  
Hyosim Kim ◽  
Frank A. Garner ◽  
Kenneth L. Peddicord ◽  
Lin Shao
Keyword(s):  
Pure Iron ◽  
Focused Ion Beam ◽  
Ion Irradiation ◽  
Ion Beam ◽  
Full Range ◽  
Peak Displacement ◽  
Free Surfaces ◽  
Projected Range ◽  
Void Swelling ◽  
Displacement Per Atom

We studied the effects of internal free surfaces on the evolution of ion-induced void swelling in pure iron. The study was initially driven by the motivation to introduce a planar free-surface defect sink at depths that would remove the injected interstitial effect from ion irradiation, possibly enhancing swelling. Using the focused ion beam technique, deep trenches were created on a cross section of pure iron at various depths, so as to create bridges of thickness ranging from 0.88 μm to 1.70 μm. Samples were then irradiated with 3.5 MeV Fe2+ ions at 475 °C to a fluence corresponding to a peak displacement per atom dose of 150 dpa. The projected range of 3.5 MeV Fe2+ ions is about 1.2 μm so the chosen bridge thicknesses involved fractions of the ion range, thicknesses comparable to the mean ion range (peak of injected interstitial distribution), and thicknesses beyond the full range. It was found that introduction of such surfaces did not enhance swelling but actually decreased it, primarily because there were now two denuded zones with a combined stronger influence than that of the injected interstitial. The study suggests that such strong surface effects must be considered for ion irradiation studies of thin films or bridge-like structures.

TEM, XRD and nanoindentation characterization of Xenon ion irradiation damage in austenitic stainless steels

2014 ◽  
Vol 454 (1-3) ◽  
pp. 168-172 ◽  
Author(s):  
H.F. Huang ◽  
J.J. Li ◽  
D.H. Li ◽  
R.D. Liu ◽  
G.H. Lei ◽  
...  
Keyword(s):  
Stainless Steels ◽  
Ion Irradiation ◽  
Austenitic Stainless Steels ◽  
Irradiation Damage

Surface roughness factor measurements of 304 and 316 stainless steels with helium ion irradiation

1981 ◽  
Vol 103 ◽  
pp. 445-449 ◽  
Author(s):  
S. Maeda ◽  
M. Mohri ◽  
M. Hashiba ◽  
T. Yamashina ◽  
M. Kaminsky
Keyword(s):  
Surface Roughness ◽  
Stainless Steels ◽  
Ion Irradiation ◽  
Roughness Factor ◽  
Helium Ion
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