Thorium‐uranium close fuel cycle in fluoride‐salt‐cooled solid‐fuel fast reactor with two recycle strategies
Sign Up to like & getrecommendations! Published in 2020 at "International Journal of Energy Research"
DOI: 10.1002/er.6168
Abstract: Fluoride‐salt‐cooled solid‐fuel fast reactor (LSFR) based on thorium fuel could achieve a self‐sustaining core which satisfies long term energy supply. In this paper, we further investigated the LSFR core neutronics characteristics for the close fuel… read more here.
Keywords: recycle; cycle; fuel cycle; fuel ... See more keywords
Phase characterization and thermal study of SrF2 and NdF3 doped fluoride salt containing 78 mol% LiF–20 mol% ThF4–2 mol% UF4
Sign Up to like & getrecommendations! Published in 2017 at "Journal of Radioanalytical and Nuclear Chemistry"
DOI: 10.1007/s10967-017-5438-0
Abstract: In this report we communicate the behavior of NdF3 and SrF2 doped in MSBR fluoride salt (78 mol% LiF–20 mol% ThF4–2 mol% UF4) up to 750 °C as observed from DTA and XRD. The eutectic composition of the fuel… read more here.
Keywords: mol lif; phase; salt; lif mol ... See more keywords
Carburization effects on the corrosion of Cr, Fe, Ni, W, and Mo in fluoride-salt cooled high temperature reactor (FHR) coolant
Sign Up to like & getrecommendations! Published in 2018 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2018.05.013
Abstract: Abstract Corrosion of structural alloys in fluoride salt cooled high temperature reactors (FHRs) is affected by the presence of carbon. The stability of the carbides of alloying elements augments their corrosion, however the same property… read more here.
Keywords: cooled high; high temperature; salt cooled; corrosion ... See more keywords
Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane
Sign Up to like & getrecommendations! Published in 2018 at "Journal of The European Ceramic Society"
DOI: 10.1016/j.jeurceramsoc.2017.09.031
Abstract: Abstract Modification process has been conducted on commercial nuclear graphite IG-110 (Toyo Tanso Co., Ltd., Japan) by impregnation and pyrolysis of polycarbosilane (PCS) solution for getting the modified IG-110 (M-IG-110) coated by dense SiC coating… read more here.
Keywords: nuclear graphite; oxidation; salt; sic coating ... See more keywords
Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2019.07.001
Abstract: Abstract Silicon carbide is widely appreciated for its high temperature strength, radiation tolerance and neutronic transparency in applications for fuel particles and core internals of nuclear reactors. In the Fluoride Salt-Cooled High Temperature Reactor, silicon… read more here.
Keywords: silicon; fluoride salt; silicon carbide; molten fluoride ... See more keywords
Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2019.03.006
Abstract: Abstract SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (Toyo Tanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor (MSR). Two kinds… read more here.
Keywords: nuclear graphite; glassy carbon; sic glassy; fluoride salt ... See more keywords
Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors
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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
Tritium Production and Partitioning from the Irradiation of Lithium-Beryllium Fluoride Salt
Sign Up to like & getrecommendations! Published in 2017 at "Fusion Science and Technology"
DOI: 10.1080/15361055.2017.1291040
Abstract: Abstract The MIT Nuclear Reactor Laboratory (NRL) has irradiated lithium-beryllium fluoride (flibe) salt as part of an on-going U.S. Department of Energy-funded Integrated Research Project to develop a Fluoride Salt High-Temperature Reactor (FHR). As part… read more here.
Keywords: irradiation; production; salt; tritium ... See more keywords
Tritium Content and Chemical Form in Nuclear Graphite from Molten Fluoride Salt Irradiations
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DOI: 10.1080/15361055.2020.1712993
Abstract: Abstract Advanced reactor applications that use a molten fluoride salt coolant and graphite moderator are under consideration as next-generation energy technologies. For molten salts with lithium or beryllium, such as flibe (2LiF-BeF2), the production of… read more here.
Keywords: molten fluoride; tritium; form; content chemical ... See more keywords