CREEP STRAIN CORRELATION FOR IRRADIATED CLADDING

Macheret, P.

United States. Department of Energy. Yucca Mountain Project Office.

关键词: Uranium;    Spent Fuels;    36 Materials Science;    Zircaloy;    11 Nuclear Fuel Cycle And Fuel Materials;   

DOI  :  10.2172/886037
RP-ID  :  CAL-EBS-MD-000015 REV 00
RP-ID  :  NA
RP-ID  :  886037

美国|英语

来源: UNT Digital Library

【 摘 要 】

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.