Effect of heating temperature on tritium retention in stainless steel type 316 L
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear materials and energy"
DOI: 10.1016/j.nme.2018.05.024
Abstract: Abstract Dependence of heating temperature on tritium retention behavior in stainless steel type 316 L (SS316L) has been examined about each process of degassing and tritium exposure. Two kinds of SS316L samples were employed: bare SS316L… read more here.
Keywords: tritium; temperature tritium; heating temperature; tritium retention ... See more keywords
Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear Materials and Energy"
DOI: 10.1016/j.nme.2019.03.005
Abstract: Plasma-facing materials for next generation fusion devices, like ITER and DEMO, will be submitted to intense fluxes of light elements, notably He and H isotopes (HI). Our study focuses on tritium (T) retention on a… read more here.
Keywords: retention; plasma facing; inventory; facing materials ... See more keywords
Dust sampling in WEST and tritium retention in tokamak-relevant tungsten particles
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear materials and energy"
DOI: 10.1016/j.nme.2020.100781
Abstract: Abstract The paper presents complementary approaches based on experimental and numerical works to address the behavior of tokamak-relevant tungsten particles loaded with tritium. Sampling of particles inside the WEST tokamak have been realized thanks to… read more here.
Keywords: tokamak relevant; tungsten particles; tritium; relevant tungsten ... See more keywords
Investigation on tritium retention and surface properties on the first wall in the large helical Device
Sign Up to like & getrecommendations! Published in 2021 at "Nuclear materials and energy"
DOI: 10.1016/j.nme.2021.100906
Abstract: Abstract In the Large Helical Device (LHD), the first deuterium plasma experiment was conducted in 2017. To investigate tritium migration in the LHD vacuum vessel, long-term material probes were installed on the first wall before… read more here.
Keywords: divertor; helical device; large helical; first wall ... See more keywords
Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors
Sign Up to like & getrecommendations! Published in 2021 at "Nuclear Technology"
DOI: 10.1080/00295450.2020.1829428
Abstract: Abstract Mitigating the release of tritium produced from neutron irradiation of molten salts containing lithium or beryllium is a technical challenge for several advanced reactor designs. In a pebble bed Fluoride-Salt-Cooled High-Temperature Reactor (FHR), tritium… read more here.
Keywords: tritium; salt cooled; fluoride salt; tritium retention ... See more keywords