COMPARISON OF CLADDING CREEP RUPTURE MODELS

Macheret, P.

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

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

DOI  :  10.2172/886036
RP-ID  :  CAL-EBS-MD-000009 REV 00
RP-ID  :  NA
RP-ID  :  886036

美国|英语

来源: UNT Digital Library

【 摘 要 】

The objective of this calculation is to compare several creep rupture correlations for use in calculating creep strain accrued by the Zircaloy cladding of spent nuclear fuel when it has been emplaced in the repository. These correlations are used to calculate creep strain values that are then compared to a large set of experimentally measured creep strain data, taken from four different research articles, making it possible to determine the best fitting correlation. The scope of the calculation extends to six different creep rupture correlations.