CREEP STRAIN CORRELATION FOR IRRADIATED CLADDING Page: 5 of 40
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1. PURPOSE
In an attempt to predict the creep deformation of spent nuclear fuel cladding under the repository
conditions, different correlations have been developed. One of them, which will be referred to as
Murty's correlation in the following, and whose expression is given in Henningson (1998), was
developed on the basis of experimental points related to unirradiated Zircaloy cladding
(Henningson 1998, p. 56). The objective of this calculation is to adapt Murty's correlation to
experimental points pertaining to irradiated Zircaloy cladding. The scope of the calculation is
provided by the range of experimental parameters characterized by Zircaloy cladding
temperature between 292*C and 420*C, hoop stress between 50 and 630 MPa, and test time
extending to 8000 h. As for the burnup of the experimental samples, it ranges between 0.478 and
64 MWd/kgU (i.e., megawatt day per kilogram of uranium), but this is not a parameter of the
adapted correlation.
This calculation is associated with engineering activity and has been developed in accordance
with a technical work plan (CRWMS M&O 2000, main body of the document and pp. 23 to 26
of Addendum A), under Office of Civilian Radioactive Waste Management (OCRWM)
procedure AP-3.12Q, Revision 0, ICN 3, Calculations.CAL-EBS-MD-000015 REV 00
January 2001
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Macheret, P. CREEP STRAIN CORRELATION FOR IRRADIATED CLADDING, report, January 23, 2001; Las Vegas, Nevada. (https://digital.library.unt.edu/ark:/67531/metadc892341/m1/5/: accessed May 5, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.