contributor author | Palazhchenko, Olga Y. | |
contributor author | Kaye, Matthew H. | |
date accessioned | 2025-04-21T10:15:21Z | |
date available | 2025-04-21T10:15:21Z | |
date copyright | 9/30/2024 12:00:00 AM | |
date issued | 2024 | |
identifier issn | 2332-8983 | |
identifier other | ners_011_02_021602.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4305808 | |
description abstract | The 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. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Investigation 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 | |
type | Journal Paper | |
journal volume | 11 | |
journal issue | 2 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4066340 | |
journal fristpage | 21602-1 | |
journal lastpage | 21602-8 | |
page | 8 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 011 ):;issue: 002 | |
contenttype | Fulltext | |