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Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage

To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integrity during interim-dry storage and subsequent transport, zirconium alloy cladding tubes were hydrogen-charged to generate 250 ppm and 500 ppm hydrogen contents, simulating spent nuclear fuel degradat...

Täydet tiedot

Tallennettuna:
Bibliografiset tiedot
Päätekijät: Ki-Nam Jang, Hyun-Jin Cha, Kyu-Tae Kim
Aineistotyyppi: Artigo
Kieli:Inglês
Julkaistu: Elsevier 2017-12-01
Sarja:Nuclear Engineering and Technology
Aiheet:
Linkit:http://www.sciencedirect.com/science/article/pii/S1738573317300505
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