...S. Valance; J. Bertsch; A. M. Alam The orientation of hydrides in fuel cladding determines the anisotropic fracture behavior of Zircaloy and the failure modes of cladding tubes. Approach coupling experiments using the cladding tube deformation test and finite element analysis have successfully led...

... is, among others parameters (free growth, creep), strongly driven by corrosion. Oxide layer and hydrides precipitation could both induce an increase of the dimensional parameters. The scope of the present study is, regardless of irradiation effect, to quantify and to understand the separate effects...

...; (c) data provided by Testing Material Reactors (OSIRIS and Halden reactor) during isothermal oxidation to determine the effects of irradiation; and (d) oxidation tests performed on pre-hydrided alloys to take into account the accelerated corrosion phase occurring, in reactor, for Zircaloy-4 at high...

..., oxidation, and hydriding at high fuel burnup may degrade cladding ductility to the extent that such large ruptures are possible under severe loadings. To understand this susceptibility to failure, this study focused on mechanical testing coupled with detailed finite-element modeling and analyses. Under ring...

...Adil M. Alam; Christian Hellwig The phenomenon of stress reorientation of hydrides in fuel cladding tubes was studied with the help of a test technique named as the “cladding tube deformation test” (CTDT). Unirradiated Zircaloy-2 (Zry-2) cladding tube specimens charged with 250 ppm of hydrogen were...

...P. A. Raynaud; D. A. Koss; A. T. Motta; K. S. Chan The susceptibility of fuel cladding to failure in the case of a postulated reactivity-initiated accident may be determined by crack initiation within a hydride blister or rim and subsequent crack growth through the thickness of the cladding...

... during cooling from 400°C under stress (190 MPa), precipitated all visible hydrides in the radial direction. H. Tsai1 and M. C. Billone2 Journal of ASTM International, January 2006, Vol. 3, No. 1 Paper ID JAI12425 Available online at www.astm.org Thermal Creep of Irradiated Zircaloy Cladding ABSTRACT...

...P Bossis; D Pêcheur; K Hanifi; J Thomazet; M Blat The corrosion and hydriding behavior of M5 and low tin Zircaloy-4 in PWR have been compared at high burn-ups (>70 GWd/t). Whereas low tin Zircaloy-4 reached about 90 μm in oxide thickness and is subjected to significant precipitation of hydride...