Results 21 to 30 of about 467,366 (245)

Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation

, 2023
The irradiation hardening behavior and the void swelling behavior of the Japanese reduced activation ferritic/martensitic steel, i.e. F82H IEA heat, were investigated by using single- and dual-ion irradiation experiments in this study.
Ando Masami, Hamaguchi Dai, Nozawa Takashi, Watanabe Yoshiyuki   +3 more
core   +1 more source

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

Radiation damages in CMOS image sensors: testing and hardening challenges brought by deep sub-micrometer CIS processes [PDF]

, 2010
This paper presents a summary of the main results we observed after several years of study on irradiated custom imagers manufactured using 0,18 µm CMOS processes dedicated to imaging.
Goiffon, Vincent, Magali Estribeau, Estribeau, Magali, Virmontois, Cédric, Pinel, Philippe, Philippe Pinel, Pierre Magnan, Corbière, Franck, Cédric Virmontois, Vincent Goiffon, Cervantes, Paola, Paola Cervantes, Franck Corbière, Magnan, Pierre   +13 more
core   +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

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

Radiation Effects on CMOS Image Sensors With Sub-2 µm Pinned Photodiodes [PDF]

, 2012
CMOS image sensor hardness under irradiation is a key parameter for application fields such as space or medical. In this paper, four commercial sensors featuring different technological characteristics (pitch, isolation or buried oxide) have been ...
Place, Sébastien, Goiffon, Vincent, Roy, François, Carrere, Jean-Pierre, Magnan, Pierre, Allegret, Stephane   +5 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

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

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