Corrosion Behavior of Zircaloy Fuel Cladding Under Hydrogen and Nitrogen Exposure at Eutectic Temperatures
Rohmad Sigit, Juan Carlos Sihotang, Fajar Al Afghani

Research Center for Nuclear Material and Radioactive Waste Technology-BRIN

Abstract

Abstract is submitted as file

Keywords: corrosion, zircaloy, EIS, cladding, eutectic

Topic: Nuclear Technology