Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1566005 | Journal of Nuclear Materials | 2013 | 8 Pages |
Abstract
The optimum specimen length was determined by using ductile and embrittled tubes with various lengths of 30-60Â mm and was found to be around 45Â 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
Authors
Masafumi Nakatsuka, Makoto Aita, Kan Sakamoto, Toru Higuchi,