2015
DOI: 10.1016/j.jnucmat.2015.03.004
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Corrosion of 316 stainless steel in high temperature molten Li2BeF4 (FLiBe) salt

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Cited by 90 publications
(41 citation statements)
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“…Pi Li et al researched the permeation behaviors of tritium in the candidate structural materials of FHRs with the method of gas‐driven permeation . Guiqiu Zheng examined the corrosion behavior of 316 stainless steel and Hastelloy N before and after neutron irradiation . However, little work has been carried out on establishing a comprehensive model about tritium transport behaviors in FHRs.…”
Section: Introductionmentioning
confidence: 99%
See 1 more Smart Citation
“…Pi Li et al researched the permeation behaviors of tritium in the candidate structural materials of FHRs with the method of gas‐driven permeation . Guiqiu Zheng examined the corrosion behavior of 316 stainless steel and Hastelloy N before and after neutron irradiation . However, little work has been carried out on establishing a comprehensive model about tritium transport behaviors in FHRs.…”
Section: Introductionmentioning
confidence: 99%
“…24 Guiqiu Zheng examined the corrosion behavior of 316 stainless steel and Hastelloy N before and after neutron irradiation. 25,26 However, little work has been carried out on establishing a comprehensive model about tritium transport behaviors in FHRs. John Stempien developed a primary model of tritium transport with MATLAB code, 27 but it has not been applied to analyze a reactor.…”
Section: Introductionmentioning
confidence: 99%
“…Experiments conducted by Kondo et al (2009aKondo et al ( ), (2009b for fusion reactors suggest that 316L stainless steel is a promising candidate material for the CWHE tubes due to its corrosion resistance towards Li 2 BeF 4 (flibe) foreseen for the air/SCO 2 cooled FHR design. Similarly promising results were later confirmed by Zheng et al (2015) who ran their experiments to specifically understand the corrosion behavior in FHR heat exchangers. In addition to the benevolent corrosion behavior of 316L towards flibe Ganesan and Ganesan (1998) examined the relatively good corrosion resistance of annealed 316L towards sodium, another candidate coolant for the reactor design with S-CO 2 cycle.…”
Section: Methodsmentioning
confidence: 70%
“…All three heat exchangers for steam generation are accommodated in a single unit, very similar to current boiler operations for electricity generation. Recent investigations have shown that 700 ºC is approximately the maximum limit for economically using stainless steel in designs with high temperature molten salts [35][36][37]. For this reason a slightly more conservative temperature of 675 ºC is chosen as the maximum salt temperature, i.e.…”
Section: Case Study 2: Greenfield Designmentioning
confidence: 99%