Results 1 to 10 of about 1,249,833 (230)

Fundamental Mechanisms for Irradiation-Hardening and Embrittlement: A Review

open access: yesMetals, 2019
It has long been recognized that exposure to irradiation environments could dramatically degrade the mechanical properties of nuclear structural materials, i.e., irradiation-hardening and embrittlement.
Xiazi Xiao
doaj   +3 more sources

The effect of high-pressure torsion on irradiation hardening of Eurofer-97 [PDF]

open access: yesNuclear Materials and Energy, 2023
We investigate the effect of nano-structuring by high-pressure torsion (HPT) on the irradiation performance of Eurofer-97. Material was deformed to shear strains from 0 to ∼230, and then exposed to Fe3+ irradiation doses of 0.01 and 0.1 displacements-per-
Gregory Strangward-Pryce   +3 more
doaj   +2 more sources

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

open access: yesNuclear 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   +4 more
doaj   +2 more sources

The Effect of Yttrium Addition on the Microstructure and Irradiation Hardening in V-4Cr-4Ti Alloy under Self-Ion Irradiation

open access: yesMetals, 2021
Microstructure and irradiation hardening of V-4Cr-4Ti alloys with different yttrium (Y) contents were studied by self-ion irradiation at 550 °C via TEM and nano-indentation test technology.
Hongtai Luo   +7 more
doaj   +2 more sources

Irradiation hardening of pure tungsten exposed to neutron irradiation [PDF]

open access: yesJournal of Nuclear Materials, 2016
Abstract Pure tungsten samples have been neutron irradiated in HFIR at 90–850 °C to 0.03–2.2 dpa. A dispersed barrier hardening model informed by the available microstructure data has been used to predict the hardness. Comparison of the model predictions and the measured Vickers hardness reveals the dominant hardening contribution at various ...
Xunxiang Hu   +6 more
openaire   +2 more sources

Evaluation of helium effect on ion-irradiation hardening in pure tungsten by nano-indentation method

open access: yesNuclear Materials and Energy, 2016
As-received and recrystallized pure tungsten (W) were irradiated with 6.4MeV Fe3+ up to 2dpa with or without He+ at 300°C, 500°C, 700°C and 1000°C respectively. Irradiation hardening was measured by the nano-indentation method.
Zhexian Zhang   +3 more
doaj   +2 more sources

Temperature effect of irradiation hardening behavior of 316L stainless steel by additive manufacturing

open access: yesHe jishu, 2022
BackgroundThe additive manufacturing (AM) technology is expected to apply to the field of advanced nuclear energy because of its unrivalled design freedom and short lead times.
FU Chonglong   +3 more
doaj   +1 more source

Effect of temperature history on the irradiation behavior of vanadium alloy irradiated with the MARICO-II rig in a fast reactor, JOYO

open access: yesNuclear Materials and Energy, 2022
The irradiation behavior of vanadium alloys was examined to evaluate the effect of temperature history during reactor operation. Irradiation experiments were performed in a fast reactor, Joyo, with an irradiation-temperature-controlled irradiation rig ...
Ken-ichi Fukumoto   +3 more
doaj   +1 more source

Correlation between Microstructural Change and Irradiation Hardening Behavior of He-Irradiated V–Cr–Ti Alloys with Low Ti Addition

open access: yesQuantum Beam Science, 2021
V–4Cr–xTi (x = 0 to 4) alloys were used to investigate the additional effect of Cr, Ti and interstitial impurities on the microstructural evolution in He-irradiated V–Cr–Ti alloys to minimize radioactivity after fusion neutron irradiation.
K. Fukumoto   +4 more
semanticscholar   +1 more source

Effect of cold work deformationon irradiation hardening of vanadium alloys

open access: yesNuclear Fusion, 2022
Vanadium alloys are regarded as promising candidate structural materials for the advanced blanket concept in fusion reactors due to their low activation, good high-temperature strength and, in particular, their compatibility with liquid lithium.
Xuxiao Han   +6 more
semanticscholar   +1 more source

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