Results 1 to 10 of about 15,662 (114)

The effect of nanocrystalline microstructure on deuterium transport in displacement damaged tungsten

open access: yesNuclear Materials and Energy, 2023
The influence of grain boundaries (GBs) on the deuterium (D) transport and the creation of defects in nanocrystalline tungsten (W) films deposited on a W substrate was studied.
S. Markelj   +8 more
doaj   +1 more source

Microstructural characterisation of brittle fracture initiation sites in reactor pressure vessel steels

open access: yesNuclear Materials and Energy, 2023
Neutron embrittlement of reactor pressure vessel (RPV) steels potentially limits the safe operational time of nuclear reactors. In tested RPV steel samples microcracks are known to originate from cleaved precipitates, inclusions or grain boundaries ...
Paul Chekhonin   +3 more
doaj   +1 more source

Assessment of neutron irradiation effects via PKA spectra, displacement damage, and gas production: Application to reactor pressure vessel

open access: yesNuclear Materials and Energy, 2023
Neutron irradiation damage is a major challenge for materials employed in radiation environments, such as Reactor Pressure Vessels (RPV). Based on a determined neutron flux, the present study assesses the neutron irradiation effects via Primary Knock-on ...
Shengli Chen
doaj   +1 more source

Preliminary CFD and EM analysis of the ECRH equatorial launcher port plug prototype towards the CFETR

open access: yesNuclear Materials and Energy, 2023
The CFETR is the next generation magnetic confinement tokamak, its increasing heating needs and stringent shielding requirements present new challenges for the ECRH launcher.
Dingzhen Li   +8 more
doaj   +1 more source

Irradiation hardening of FeCrAl ODS alloys with Zr/Hf addition after high-energy self-ions irradiation

open access: yesNuclear Materials and Energy, 2023
FeCrAl ODS steel is the promising candidate cladding material for the accident tolerant fuel (ATF) of the light water reactors (LWR), due to the formation of Al2O3 in alloys which could suppress the oxidation reaction with hot steam. In the present work,
Xuxiao Han   +4 more
doaj   +1 more source

Microstructure of tungsten coatings effect on deuterium plasma-driven permeation through RAFM steel

open access: yesNuclear Materials and Energy, 2023
Tungsten (W) coatings with different morphologies were deposited on CLF-1 steel by changing the sputtering time and discharge power using the magnetron sputtering method.
Kai Yang   +5 more
doaj   +1 more source

Instability of molten beryllium layers during ITER thermal quenches

open access: yesNuclear Materials and Energy, 2023
The production and dynamics of beryllium melt pools are simulated in conditions relevant to unmitigated thermal quenches in ITER. Rayleigh–Taylor instabilities fed by Lorentz forces due to induced eddy currents are found to result in significant material
L. Vignitchouk   +3 more
doaj   +1 more source

FIB line marking as a tool for local erosion/deposition/fuzz formation measurements in ASDEX Upgrade during the He campaign

open access: yesNuclear Materials and Energy, 2023
Tungsten (W) is the prime candidate for the plasma facing material in present and future fusion devices. When exposed to a plasma containing He ions, W can exhibit creation of sub-surface nano-bubbles leading to formation of nano-tendrils called fuzz ...
M. Rasiński   +12 more
doaj   +1 more source

Improving the high-temperature oxidation resistance of CrN coating by gradient deposition considering internal stress effects

open access: yesNuclear Materials and Energy, 2023
In this study, two different CrN coatings were deposited on the surface of Zr-4 via a multi-arc ion-plating method using gradient and non-gradient deposition processes.
Chuiyi Meng   +8 more
doaj   +1 more source

Spinodal decomposition and radiation damage of a FeCuMnNi high-entropy alloy

open access: yesNuclear Materials and Energy, 2023
The precipitation of Cu-rich phases during the irradiation process will reduce radiation resistance in Fe-Cu-Mn-Ni reactor pressure vessel steels. Therefore, high-entropy alloys with excellent radiation resistance are expected to replace reactor pressure
Qingwei Guo   +5 more
doaj   +1 more source

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