Zirconium (Zr) alloys, serving as fuel cladding tubes and grids for pressurized water and boiling water nuclear reactors, undergo oxidation when exposed to oxidizing environment during service, ...

In this work, SiC (Silicon carbide), FeCrAl (ferritic), SS-310 (stainless steel 310) and Zirconium are simulated by MCNPX (Monte Carlo N‐Particle eXtended) code as cladding materials in advanced PWR ...

This publication examines the phenomena of delayed hydride cracking (DHC) in Zircaloy-4 claddings and presents the results of a coordinated research project on this subject. It discusses the ...

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