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dc.contributor.authorKlok, Oksana
dc.contributor.authorLambrinou, Konstantina
dc.contributor.authorGavrilov, Serguei
dc.contributor.authorLim, Jun
dc.contributor.authorDe Graeve, Iris
dc.date.accessioned2019-02-28T11:05:30Z
dc.date.available2019-02-28T11:05:30Z
dc.date.copyright5/16/2018 12:00:00 AM
dc.date.issued2018
dc.identifier.issn2332-8983
dc.identifier.otherners_004_03_031019.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252578
dc.description.abstractThis work focuses on the effect of dissolved oxygen concentration in liquid lead-bismuth eutectic (LBE) on the onset of dissolution corrosion in a solution-annealed 316 L austenitic stainless steel. Specimens made of the same 316 L stainless steel heat were exposed for 1000 h at 450 °C to static liquid LBE with controlled concentrations of dissolved oxygen, i.e., 10−5, 10−6, and 10−7 mass%. The corroded 316 L steel specimens were analyzed by scanning electron microscopy (SEM) and energy dispersive X-ray spectroscopy (EDS). A complete absence of dissolution corrosion was observed in the steel specimens exposed to liquid LBE with 10−5 and 10−6 mass% oxygen. In the same specimens, isolated “islands” of FeCr-containing oxides were also detected, indicating the localized onset of oxidation corrosion under these exposure conditions. On the other hand, dissolution corrosion with a maximum depth of 59 μm was detected in the steel specimen exposed to liquid LBE with 10−7 mass% oxygen. This suggests that the threshold oxygen concentration associated with the onset of dissolution corrosion in this 316 L steel heat lies between 10−6 and 10−7 mass% oxygen for the specific exposure conditions (i.e., 1000 h, 450 °C, static liquid LBE).
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleEffect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C
dc.typeJournal Paper
dc.journal.volume4
dc.journal.issue3
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4039598
dc.journal.fristpage31019
dc.journal.lastpage031019-7
dc.treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003
dc.contenttypeFulltext


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