2019
DOI: 10.1016/j.nucengdes.2019.110232
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Experimental investigation of alumina coating as tritium permeation barrier for molten salt nuclear reactors

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Cited by 21 publications
(9 citation statements)
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“…The concentration of active sites available at any instant of time S ½ is given by Equation (35), where S 0 is the initial concentration of active sites, Al À S ½ is the concentration of sites occupied by aluminium, Al 2 O 3 À S ½ is the concentration of sites occupied by alumina, and Fe 2 O 3 À S ½ is the concentration of sites occupied by iron oxide.…”
Section: Specie Mass Balance Solvermentioning
confidence: 99%
See 1 more Smart Citation
“…The concentration of active sites available at any instant of time S ½ is given by Equation (35), where S 0 is the initial concentration of active sites, Al À S ½ is the concentration of sites occupied by aluminium, Al 2 O 3 À S ½ is the concentration of sites occupied by alumina, and Fe 2 O 3 À S ½ is the concentration of sites occupied by iron oxide.…”
Section: Specie Mass Balance Solvermentioning
confidence: 99%
“…[27] The general techniques used for alumina coating on carbon steels are physical vapour deposition, chemical vapour deposition (CVD), sol-gel, plasma electrolytic oxidation, thermal spray, and pack cementation. [27][28][29][30][31][32][33][34][35][36][37][38] In the present work, a fluidizationbased CVD process is employed owing to its ability to achieve simultaneous deposition of alumina on inner and outer surfaces of a tubular carbon steel substrate. Fluidized bed sublimation and induction heating are employed to optimize precursor inventory.…”
Section: Introductionmentioning
confidence: 99%
“…At high temperatures, tritium readily diffuses into metal structures such as the reactor pressure vessel, piping, and heat exchangers, eventually creating transport pathways through the reactor and opening up the possibility of environmental release. Zheng et al 151 found that alumina coatings on 316 SS tubing significantly reduced the permeability of tritium. Tritium permeation barriers deposited via plasma thermal spray and consisting of a NiCr topcoat, a NiCr + alumina bond coat, and a 316 SS substrate were exposed to neutron irradiation to study their tritium permeation at 700 °C, proving successful at decreasing the tritium's permeability.…”
Section: Tbc Applicationsmentioning
confidence: 99%
“…A test blanket module (TBM) with the main function of tritium breeding is indispensable [3]. To ensure a steady-state operation of a fusion reactor tritium self-sufficiency is important, which is ensured by the nuclear reaction between neutron and lithium [4]. Tritium has strong permeability in the structural material (RAFM), due to * Author to whom any correspondence should be addressed.…”
Section: Introductionmentioning
confidence: 99%