DEGRADATION MODES OF ALLOY 22 IN YUCCA MOUNTAIN REPOSITORY CONDITIONS | Zendy

Fuan Hua | Zendy; G.M. Gordon | Zendy; Raúl B. Rebak | Zendy

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DEGRADATION MODES OF ALLOY 22 IN YUCCA MOUNTAIN REPOSITORY CONDITIONS

Author(s) -

Fuan Hua,

G.M. Gordon,

Raúl B. Rebak

Publication year - 2005

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/860241

Subject(s) - corrosion , alloy , degradation (telecommunications) , radioactive waste , cracking , materials science , stress corrosion cracking , shield , metallurgy , containment (computer programming) , spent nuclear fuel , yucca , composite material , nuclear engineering , geology , waste management , engineering , petrology , telecommunications , computer science , programming language , botany , biology

The nuclear waste package design for Yucca Mountain (Nevada, USA), in its current configuration, consists of a double wall cylindrical container fabricated using a highly corrosion resistant Ni-based Alloy 22 for the outer barrier and type 316 stainless steel for the inner structural vessel. A mailbox-shaped drip shield fabricated primarily using Ti Grade 7 will cover the waste packages. The environmental degradation of the relevant materials have been extensively studied and modeled for over ten years. This paper reviews the state-of-the-art understanding of the degradation modes of Alloy 22 (N06022) due to its interaction with the predicted in-drift mountain conditions including temperature and types of electrolytes. Subjects discussed include thermal aging and phase stability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced cracking

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