Article ID Journal Published Year Pages File Type
1566005 Journal of Nuclear Materials 2013 8 Pages PDF
Abstract
The optimum specimen length was determined by using ductile and embrittled tubes with various lengths of 30-60 mm and was found to be around 45 mm for typical BWR fuel rods. During the OEB test, internal pressure and diametral expansion were monitored to obtain the basic mechanical performance properties of the fuel cladding such as yield stress, ultimate strength, as well as the true hoop stress-hoop strain curve.
Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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