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Published in 2018 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2017.11.018
Abstract: Abstract Allowable cladding peak temperatures for spent fuel cladding integrity in interim dry storage were investigated, considering hydride reorientation and mechanical property degradation behaviors of unirradiated and neutron irradiated Zr-Nb cladding tubes. Cladding tube specimens…
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Keywords:
temperature;
cladding peak;
dry storage;
interim dry ... See more keywords