General Corrosion of Inconel Alloy 625®in Simulated Superheat Reactor Environment
- 1 July 1967
- journal article
- research article
- Published by Taylor & Francis in Nuclear Applications
- Vol. 3 (7) , 418-432
- https://doi.org/10.13182/nt67-a27840
Abstract
INCONEL alloy 625® fuel-cladding material has been corrosion-tested under heat-transfer conditions at metal temperatures up to 1500°F (816°C) in specially designed out-of-pile superheat facilities. The hydrogen and oxygen contents of the steam were controlled to simulate those found in boiling-water-reactor systems.The corrosion data from the 3600-h heat-transfer tests indicated good corrosion resistance up to the 1500°F metal temperature tested. A compositionally changed layer developed at the metal-oxide interface that appeared to reach a maximum depth at the higher temperatures.The heat-transfer test data indicated that except for a small buildup of oxide during the initial nonlinear transient corrosion period, most of the oxide formed in corrosion was carried downstream by the superheated steam.The uniform corrosion experienced by the INCONEL-625 when exposed isothermally to 1050 and 1150°F (566 and 621°C) for 10 000 h indicates an initially high-corrosion rate that decreases to a lower constant rate ...Keywords
This publication has 3 references indexed in Scilit:
- Surface AnalysisNuclear Applications, 1967
- General Corrosion of Stainless Steels and Nickel Base Alloys Exposed Isothermally in Superheated SteamCorrosion, 1965
- General Corrosion of Incoloy-800® in Simulated Superheat Reactor EnvironmentNuclear Applications, 1965