2019
DOI: 10.18321/ectj787
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Methodology of Corrosion Testing of Nuclear and Fusion Reactors Materials Using TGA/DSC and MS Complex Techniques

Abstract: The behavior of structural materials of nuclear and fusion reactors during operation largely determines their safe and economical work. Structural materials of nuclear and fusion reactors are operating under conditions of interaction with various chemical active elements (gases, vapor-gas mixtures, fission products, etc.) in a wide temperature range; they are subject to high requirements in terms of their thermal and corrosion resistance. This paper presents the new methodology of complex studies on structural… Show more

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Cited by 14 publications
(2 citation statements)
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“…Preliminarily, using calculation methods, the ratios of the amount of lithium and tin necessary for the manufacture of the tin-lithium alloy with the specified parameters were determined. After the calculations, weighed portions of these metals were loaded into the experimental device, and prototypes were manufactured in accordance with the previously developed technological procedures [15]. In total, three types of prototypes of a tin-lithium alloy with different contents of lithium atoms (20,25, and 27 at.…”
Section: Experimental Partmentioning
confidence: 99%
“…Preliminarily, using calculation methods, the ratios of the amount of lithium and tin necessary for the manufacture of the tin-lithium alloy with the specified parameters were determined. After the calculations, weighed portions of these metals were loaded into the experimental device, and prototypes were manufactured in accordance with the previously developed technological procedures [15]. In total, three types of prototypes of a tin-lithium alloy with different contents of lithium atoms (20,25, and 27 at.…”
Section: Experimental Partmentioning
confidence: 99%
“…На сегодняшний день на установке ТиГрА были проведены исследования по определению теплофизических характеристик (теплоемкости, температуры плавления, теплоты фазовых переходов и др.) образцов оловянно-литиевой эвтектики различного состава [11][12][13][14]. Также исследовалась высокотемпературная коррозия графита марки IG-110, используемого в реакторных установках [15].…”
Section: Introductionunclassified