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Published in 2018 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2018.02.085
Abstract: Abstract W–Nb alloys were prepared using machine milling and spark plasma sintering. Field–emission scanning electron microscopy, high–resolution transmission electron microscopy were used to characterize the samples. Thermal desorption spectroscopy was used to measure the deuterium…
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Keywords:
deuterium retention;
microscopy;
retention alloys;
content increased ... See more keywords
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Published in 2017 at "Intermetallics"
DOI: 10.1016/j.intermet.2016.11.005
Abstract: Abstract Beryllium intermetallic compounds (beryllides), such as Be 12 Ti and Be 12 V, are the most promising advanced neutron multipliers in demonstration (DEMO) fusion power reactors because of higher stability, lower retention, and swelling.…
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Keywords:
deuterium retention;
intermetallic compounds;
beryllium intermetallic;
retention ... See more keywords
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Published in 2018 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2018.01.006
Abstract: Abstract The behavior of tungsten-vanadium (W-V) alloys fabricated by powder metallurgy as a plasma facing material has been studied. W-V alloys with different vanadium concentrations (5 and 10 wt %) manufactured by hot pressing (HP) were…
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Keywords:
deuterium retention;
plasma;
deuterium;
vanadium ... See more keywords
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Published in 2020 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2020.152321
Abstract: Abstract Tritium permeation and retention are serious problems in D-T fusion reactors from the viewpoint of fuel efficiency and radiological safety. Functional ceramic coatings have been intensively studied for the development of tritium permeation barriers…
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Keywords:
ceramic coatings;
retention;
deuterium retention;
deuterium ... See more keywords
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Published in 2021 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2020.152749
Abstract: Abstract To investigate systematically the effects of Re and other elements on deuterium (D) retention, W and binary W-alloys (Re, Mo and Ta) were irradiated with 6.4 MeV Fe ions at high temperatures (1073–1273 K) and…
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Keywords:
irradiated high;
deuterium retention;
retention binary;
alloys irradiated ... See more keywords
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Published in 2021 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2021.153139
Abstract: Abstract Beryllium, as the material of choice for the ITER first wall, will be subject to high energy neutrons during the operation of the fusion device. Such irradiation will create displacement damage in the crystal…
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Keywords:
beryllium;
retention;
irradiated beryllium;
deuterium retention ... See more keywords
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Published in 2017 at "Nuclear materials and energy"
DOI: 10.1016/j.nme.2016.11.010
Abstract: Abstract Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by W ions and exposed to D atoms at five different temperatures from 450 K to 1000 K. In order to obtain information…
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Keywords:
deuterium retention;
energy;
sequential damaging;
compared sequential ... See more keywords
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Published in 2018 at "Nuclear Materials and Energy"
DOI: 10.1016/j.nme.2018.11.010
Abstract: Abstract The use of tin (Sn) as a liquid metal for plasma facing components has been recently proposed as a solution to the high heat load issue on the divertor target plates in nuclear fusion…
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Keywords:
deuterium retention;
liquid;
erosion;
samples exposed ... See more keywords
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Published in 2019 at "Nuclear Materials and Energy"
DOI: 10.1016/j.nme.2018.12.032
Abstract: Abstract The tungsten “heavy alloy” HPM 1850, a liquid-phase sintered composite material with two weight percent Ni and one weight percent Fe, as well as the self-passivating tungsten alloy W-10Cr-0.5Y, a high temperature oxidation resistant…
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Keywords:
weight percent;
deuterium retention;
thermal desorption;
deuterium ... See more keywords
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Published in 2021 at "Nuclear materials and energy"
DOI: 10.1016/j.nme.2021.100928
Abstract: Abstract Nitrogen is a candidate for impurity seeding to reduce the edge plasma temperature for ITER’s tungsten divertor. Radiation characteristics and plasma performance are improved with N compared to other candidates neon and argon, however…
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Keywords:
spectroscopy;
retention;
simultaneous irradiation;
nitrogen ... See more keywords
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Published in 2017 at "Fusion Science and Technology"
DOI: 10.1080/15361055.2016.1273699
Abstract: Abstract Understanding and managing D retention in plasma facing components is essential for tritium safety in fusion reactors. Neutron irradiated and virgin low carbon arc cast (LCAC) Mo, as well as Mo foil samples with…
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Keywords:
deuterium retention;
helium neutron;
retention helium;
neutron irradiated ... See more keywords