Post-irradiation tritium recovery from lithium ceramic breeder materials

Post-irradiation tritium recovery from lithium ceramic breeder materials

Auteur : J. M. Miller

Date de publication : 1986

Éditeur : Atomic Energy Of Canada Limited

Nombre de pages : Non disponible

Résumé du livre

The individual influence of hydrogen content and graphite coating on the iodine stress corrosion cracking susceptibility of zirconium alloys has been investigated using the stressed c-ring and fuel swelling simulation testing techniques. such parameters as hydrogen content, iodine concentration, type of graphite coating, alloy composition and condition of tubing have been examined. fracture topography has been characterized both by optical microscopy and scanning electron microscopy. models have been proposed to account for the resistance to iodine stress corrosion cracking provided by both hydrogen and to a lesser extent, graphite coatings.

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