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Nuclear Materials and Energy
Title
Publication Date
Language
Citations
Nuclear Materials and Energy
2017/05/01
English
Microstructural evolution in ODS-EUROFER steel caused by high-dose He ion implantations with systematic variation of implantation parameters
2023/06/01
English
Absence of synergistic effects in quasi-simultaneous sputtering of tungsten by Ar and D ions
2023/06/01
English
Beryllium intermetallics: Industrial experience on development and manufacture
2023/06/01
English
Catalyzed oxidation of IG-110 nuclear graphite by simulated fission products Ag and Pd nanoparticles
2023/06/01
English
The effect of High-Temperature Pre-Damage on Vacancy-Type defects and deuterium retention in tungsten
2024/03/01
English
3D benchmark experiments of tritium in tungsten for tritium measurements by detecting β-ray induced X-rays
English
Study of hydrogen sorption and desorption processes of zirconium beryllide ZrBe2
English
Effects of impurities on stability of TiC, TaC and ZrC particles in tungsten
English
Microstructure evolution of γ-Al2O3/FeAl tritium permeation barrier coatings under 6.4 MeV Fe3+ ion irradiation
2024/03/01
English
Study on irradiation hardening by He+ and subsequent V/self-ion irradiation in V-4Cr-4Ti under near-service conditions
2024/03/01
English
Deuterium reclamation from C-Si codeposits using thermo-oxidation
2024/03/01
English
A comprehensive investigation on the physical properties of SiC polymorphs for high-temperature applications: A DFT study based on GGA and hybrid HSE06 exchange correlation functionals
2024/03/01
English
Effects of beam scanning modes on ion-irradiated iron microstructure
2024/03/01
English
D retention in e-beam powder-bed fused (3-D printed) tungsten exposed to high-flux deuterium plasma in Pisces-RF
English
First study of the location of deuterium in displacement-damaged tungsten by nuclear reaction analysis in channeling configuration
English
Multiscale computational study to predict the irradiation-induced change in engineering properties of fusion reactor materials
English
Reaction kinetics of Li4SiO4 and Li4Ti5O12 in biphasic breeder ceramics after lithium burn-up
English
Editorial for the Special Issue on EUROFER97
2024/04/01
English
Experimental investigation on heat transfer characteristics of a novel hypervapotron channel for divertor target in nuclear fusion reactors
English
Damage behavior of additive manufacturing 316L stainless steel irradiated with Fe ions
English
In-situ observation of restoration of tungsten plate via high-temperature confocal laser scanning microscopy
English
Mechanical and helium swelling responses of K-RAFM steels to Fe ion irradiation and helium implantation
English
Development of a tritium release system for ceramic tritium breeder pebbles irradiated by high intensity DT fusion neutron Generator at INEST
English
Comparative study of microstructural evolution in W-3Re alloy under high-temperature conditions: High heat flux loading versus furnace heating
English
Development of the WAter-interface Permeation In Tritium-exposed materIals (Wapiti) tritium experiment and preliminary Eurofer97 results
2024/03/01
English
The effect of ramp heating on the microstructure and surface chemistry of APMT FeCrAl alloy
2024/03/01
English
Study of irradiation-induced vacancy-type defects in tungsten using positron annihilation spectroscopy
2023/12/01
English
Experimental study of the isotope effect of the permeability in structural steels for fusion reactors: Eurofer and SS316
2024/03/01
English
Morphological damage to tungsten eroded by abrasive water jet
2023/12/01
English
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