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
    Volume 6, Issue 3 (March 2009)

    Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments

    (Received 25 June 2008; accepted 17 January 2009)

    Published Online: 20 February 2009


      Format Pages Price  
    PDF (672K) 17 $25   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 requirement of spent nuclear fuel is to maintain its structural integrity at all times to enable its safe and efficient handling during storage, transportation, and placement in a deep geological repository. In Canada, commercial spent fuel is currently stored in light water pools for about ten years before being transferred to dry storage where storage may extend up to 100 years. Investigations on the fuel structural integrity evolution during dry storage are being performed for spent CANDU fuel bundles. A CANDU nuclear fuel bundle is a cylindrical assembly approximately 0.1 m in diameter and 0.5 m in length made of 28 or 37 fuel elements held together by welding two endplates at both ends. The welds have a circular notch of less than 10 μm diameter. Significant hydraulic, mechanical, and thermal loads during bundle irradiation in the reactor may lead to bundle deformation, which when coupled with the sharp weld notch can result in significant stress enhancement at the notch tip and possibly activate delayed hydride cracking (DHC) during dry storage. To better understand the stress levels in CANDU fuel during dry storage, a finite element model of CANDU fuel bundles is under development. The stress distribution in the bundle and the stress intensity factor at each weld notch can be evaluated by the model for the spent fuel geometry and dry storage conditions. This paper discusses the agreement between the finite element model and validation experiments using unirradiated 28-element CANDU fuel bundles tested in the elastic and plastic regime.

    Author Information:

    Lampman, Timothy J.
    AMEC NSS, Toronto, Ontario

    Popescu, Adrian
    AMEC NSS, Toronto, Ontario

    Freire-Canosa, Jose
    Nuclear Waste Management Organization, Toronto, Ontario

    Stock #: JAI101985


    DOI: 10.1520/JAI101985

    Title Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments
    Symposium ,
    Committee E10