Results 31 to 40 of about 5,873 (297)

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

Nuclear Materials and Energy, 2021
Oxide dispersion strengthened (ODS) Cu alloys are expected to have high strength and superior irradiation resistance that are necessary characteristics for the divertor components of fusion reactors.
Yuchen Liu, Sosuke Kondo, Hao Yu, Kiyohiro Yabuuchi, Ryuta Kasada   +4 more
doaj   +1 more source

Effect of Annealing on Microstructures and Hardening of Helium-Hydrogen-Implanted Sequentially Vanadium Alloys

Nanoscale Research Letters, 2018
The effect of post-irradiation annealing on the microstructures and mechanical properties of V-4Cr-4Ti alloys was studied. Helium-hydrogen-irradiated sequentially V-4Cr-4Ti alloys at room temperature (RT) were undergone post-irradiation annealing at 450 °
Shaoning Jiang, Zhiming Wang
doaj   +1 more source

Neutron irradiation hardening and microstructure changes in Fe–Mn binary alloys [PDF]

, 2011
Irradiation hardening and microstructure changes in Fe–Mn binary alloys were investigated after neutron irradiation at 290 °C and up to 0.13 dpa. Significant irradiation hardening comparable to that of Fe–1 at.%Cu alloy was observed in Fe–1 at.%Mn alloy.
Masashi Saito, Akihiko Kimura, Ryuta Kasada, Kimura, Akihiko, Saito, Masashi, Kiyohiro Yabuuchi, Yabuuchi, Kiyohiro, Kasada, Ryuta   +7 more
core   +1 more source

Atom probe examinations of Zircaloy irradiated at nominally 358 °C

Nuclear Materials and Energy, 2019
Zircaloy-2 and Zircaloy-4 were neutron irradiated at 358 °C in the high flux isotope reactor (HFIR) to a neutron fluence of 29.6 × 1024 n/m2 (E > 1 MeV) and the resultant irradiation hardening was measured by tensile testing.
B.V. Cockeram, P.D. Edmondson, K.J. Leonard, B.F. Kammenzind, J.L. Hollenbeck   +4 more
doaj   +1 more source

Indentation testing on 3 MeV proton irradiated tungsten

Nuclear Materials and Energy, 2020
Tungsten samples have been irradiated with 3 MeV protons with dose rates of 1×10-04 to 5×10-05 dpa/s to doses of 0.01–0.67 dpa at 360 K in a pilot experiment. Micro- and macro-indentation were used to measure irradiation hardening in the samples.
R. Rayaprolu, S. Möller, R. Abernethy, M. Rasinski, J.C. Haley, Ch. Linsmeier   +5 more
doaj   +1 more source

Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditions [PDF]

, 2021
Ten Eurofer97 steel variants, produced by non-standard fabrication-processing routes and modified alloying chemistries, were studied by neutron irradiations in the high flux isotope reactor. The irradiations were performed to ITER-TBM relevant conditions
Rieth M., Terentyev D., Reed J., Graening T., Katoh Y., Puype A., Zinkle S. J., Henry J., Chen X., Bhattacharya A., Geringer J. W., Pilloni L., Byun T. S.   +12 more
core   +1 more source

Damage characteristics of selective laser melted 304L stainless steel under Xe ion irradiation

He jishu, 2021
BackgroundOwing to its excellent mechanical properties and corrosion resistance, 304L stainless steel is widely used as the core structure material in advanced nuclear power systems.PurposeThis study aims to investigate the damage characteristics of ...
LI Ying, LI Jianjian, FU Chonglong, BAI Juju, HOU Juan, LIN Jun, DAI Zhimin   +6 more
doaj   +1 more source

The Effect of Rhenium Content on Microstructural Changes and Irradiated Hardening in W-Re Alloy under High-Dose Ion Irradiation

Nanomaterials, 2023
An amount of 100 dpa Si2+ irradiation was used to study the effect of transmutation rhenium content on irradiated microscopic defects and hardening in W-xRe (x = 0, 1, 3, 5 and 10 wt.%) alloys at 550 °C.
Fengfeng Luo, Hongtai Luo, Qiuxiang Liu, Liang Zhou, Wenbin Lin, Ziyang Xie, Liping Guo   +6 more
doaj   +1 more source

Analysis of Radiation Hardening Effect of Ferritic Martensitic Steel Based on Bayesian Optimization

Crystals
Ferritic/martensitic (F/M) steel is a candidate material for key structures in fourth-generation nuclear energy systems (such as fusion reactors and fast reactors).
Yue He, Jiaming Bao, Shi Wu, Bing Bai, Xinfu He, Wen Yang   +5 more
doaj   +1 more source

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

, 2010
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 ...
Akihiko Kimura, Ryuta Kasada, Masami Ando, Hiroyasu Tanigawa, Kiyohiro Yabuuchi, Dai Hamaguchi, Yoshiyuki Takayama   +6 more
core   +1 more source