You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.

    If you are an ASTM Compass Subscriber and this document is part of your subscription, you can access it for free at ASTM Compass

    Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance

    Published: 01 February 2018

      Format Pages Price  
    PDF (3.45 MB) 33 $25   ADD TO CART
    Complete Source PDF (89.22 MB) 1309 $279   ADD TO CART

    Cite this document

    X Add email address send
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word


    A review is presented of work performed in our group over the years in the areas of radiation damage, corrosion, hydrogen pickup, hydriding, and the mechanical behavior of zirconium alloy nuclear fuel cladding with the goal of developing a greater mechanistic understanding of cladding performance in service.


    zirconium, cladding, fuel performance, radiation damage, corrosion, hydriding, hydrogen pickup, mechanical properties

    Author Information:

    Motta, Arthur T.
    Pennsylvania State University, Dept. of Mechanical and Nuclear Engineering, University Park, PA

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP159720160095