Deuterium retention in tungsten and reduced activation steels after 3 MeV proton irradiation
نویسندگان
چکیده
منابع مشابه
ANALYSIS OF A CLAD TUNGSTEN TARGET AFTER IRRADIATION IN AN 800 MeV PROTON BEAM
For the Accelerator Production of Tritium (APT) and the Accelerator Driven Transmutation Facility (ADTF), tungsten is being proposed as a target material to produce neutrons. Previous work showed that the mechanical properties of tungsten are degraded from irradiation in a neutron flux but little work had been performed on the irradiation of tungsten in a high energy proton beam. In this study,...
متن کاملThe High Temperature Tensile Properties of Ferritic-martensitic and Austenitic Steels after Irradiation in an 800 Mev Proton Beam
This study examines the effect of tensile test temperatures ranging from 50°C to 600°C on the tensile properties of a modified 9Cr-1Mo ferritic steel (T91) and a 316L stainless steel (SS) after high energy proton irradiation at about 35°C-67°C. After 1-3 dpa, the proton-irradiated T91 steel was tensile tested at temperatures from 50°C to 600°C. It was observed that the yield strength and ultima...
متن کاملDeuterium diffusion and retention in a tungsten-carbon multilayer system
A tungsten-carbon multilayer system deposited by magnetron sputtering was used as a model system to study deuterium diffusion in tungsten, carbon and related carbides. After deposition the as-deposited multilayer films were annealed at different temperatures to achieve different structures. The structural changes due to annealing were investigated by Rutherford backscattering spectrometry and X...
متن کاملImpact of beryllium surface layers on deuterium retention in tungsten
In ITER mixed Be/W layers are likely to form and their retention behavior is unknown. A series of ITER-grade tungsten samples have been exposed in PISCES-B to deuterium plasma at 300oC, with and without beryllium impurity seeding of the plasma. If the beryllium concentration is small, the majority of the incident beryllium is re-eroded from the sample surface and only a few nm thick layer of mi...
متن کاملStrongly reduced penetration of atomic deuterium in radiation-damaged tungsten.
Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias conditions. We observe that the fraction of deuterium that penetrates is only 10(-5)-10(-7) of the plasma flux and strongly dependent on the local surface temperature. We propose that deuterium does not directly penetrate bulk tungsten but that it thermalizes at the surface, where it forms a protective...
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ژورنال
عنوان ژورنال: Nuclear Materials and Energy
سال: 2020
ISSN: 2352-1791
DOI: 10.1016/j.nme.2020.100742