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dc.contributor.authorPalazhchenko, Olga Y.
dc.contributor.authorKaye, Matthew H.
dc.date.accessioned2025-04-21T10:15:21Z
dc.date.available2025-04-21T10:15:21Z
dc.date.copyright9/30/2024 12:00:00 AM
dc.date.issued2024
dc.identifier.issn2332-8983
dc.identifier.otherners_011_02_021602.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4305808
dc.description.abstractThe Zircaloy alloy system (1.2–1.7 wt.% Sn) provides an excellent basis to study the effect of temperature on Pourbaix diagrams, as Zircaloy fuel rods in a CANadian Deuterium UraniumTM (CANDU) reactor are exposed to an aqueous phase coolant in the range 250 °C (523.15 K) to 310 °C (583.15 K). In addition to its presence in Zircaloy, much of the thermochemical data for tin, particularly for the aqueous species, is unavailable or uncorroborated. This paper presents tin Pourbaix diagrams at 85 °C (358.15 K) alongside the reconstructed 25 °C (298.15 K) diagram. Solid-aqueous phase SnO2 equilibria were used to determine thermochemical data for tin +IV species in a batch vessel with in situ pH measurement. Solubilities were used to calculate the Gibbs energies of Sn complexes. The SnOH3+ and Sn(OH)5− species were incorporated into the 25 °C and 85 °C diagrams.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleInvestigation of Metal-H2O Systems at Elevated Temperatures: Part II. SnO2(s) Solubility Data and New Sn Pourbaix Diagrams at 298.15 K and 358.15 K
dc.typeJournal Paper
dc.journal.volume11
dc.journal.issue2
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4066340
dc.journal.fristpage21602-1
dc.journal.lastpage21602-8
dc.page8
dc.treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 011 ):;issue: 002
dc.contenttypeFulltext


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