Retention and enrichment of a model system for mixed layers, tungsten-containing carbon films (a-C:W), were investigated with respect to the interaction with D ions. a-C:W was exposed to a mass-separated, mono-energetic D beam (200 eV/D, 1.2·1015 D·cm−2·s−1). The W concentra-tion in the films (0-7.5 at%), the specimen temperature during D beam exposure (300- 1300K) and the fluence (Φ) of incident D (1015- 1020 D·cm−2) were varied. Analysis of retention and enrichment were performed by nuclear reaction analysis and Rutherford backscattering spec-trometry, respectively. At 300K and fluences up to 1019 D·cm−2, the increase of the D inven-tory with fluence in a-C:W cannot be distinguished from a-C and pyrolytic graphite, e.g., above ∼1017 D·cm−...
Deuterium retention in Toughened, Fine-Grained Recrystallized W (TFGR W-1.1 wt%TiC) was studied, com...
Samples made of tungsten (W) doped either with titanium carbide (W-1.1TiC) or tantalum carbide (W-3....
Abstract Deuterium retention studies are presented for nanostructured tungsten films exposed to high...
Tungsten (W) targets have been exposed to high density (ne 4 × 1019 m-3), low temperature (Te 3 eV) ...
The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter o...
Deuterium retention in two types of polycrystalline tungsten was studied as a function of ion fluenc...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
Refractory materials are being considered potential candidates to build the first wall of the fusion...
Deuterium retention in Toughened, Fine-Grained Recrystallized W (TFGR W-1.1 wt%TiC) was studied, com...
Samples made of tungsten (W) doped either with titanium carbide (W-1.1TiC) or tantalum carbide (W-3....
Abstract Deuterium retention studies are presented for nanostructured tungsten films exposed to high...
Tungsten (W) targets have been exposed to high density (ne 4 × 1019 m-3), low temperature (Te 3 eV) ...
The paper reviews hydrogen isotope retention and migration in tungsten (W). Due to a large scatter o...
Deuterium retention in two types of polycrystalline tungsten was studied as a function of ion fluenc...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by...
To understand the deuterium (D) bulk retention behavior in plasma facing materials under reactor-rel...
Two sets of identical tungsten (W) targets are irradiated at 300K with 12.3MeV W4+ ions to peak dama...
The effects of particle flux and exposure temperature on surface modifications and deuterium (D) ret...
grantor: University of TorontoFor deuterium implantation of pure W foil at 300 K, the amou...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The follow...
Refractory materials are being considered potential candidates to build the first wall of the fusion...
Deuterium retention in Toughened, Fine-Grained Recrystallized W (TFGR W-1.1 wt%TiC) was studied, com...
Samples made of tungsten (W) doped either with titanium carbide (W-1.1TiC) or tantalum carbide (W-3....
Abstract Deuterium retention studies are presented for nanostructured tungsten films exposed to high...