Evaluation of Tritium Content and Release from Pressurized Water Reactor Fuel Cladding

Research output: Other contribution › Technical Report

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@misc{15863a43be7a466aa319ae1a6474d168,

title = "Evaluation of Tritium Content and Release from Pressurized Water Reactor Fuel Cladding",

author = "Sharon Robinson and Marc Chattin and Joseph Giaquinto and Robert Jubin",

note = "ORNL/LTR-2015/425 Unclassified, Non Sensitive",

year = "2015",

month = sep,

doi = "10.2172/1223668",

language = "American English",

type = "Other",

}