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Title: A Review Corrosion of TI Grade 7 and Other TI Alloys in Nuclear Waste Repository Environments

Abstract

Titanium alloy degradation modes are reviewed in relation to their performance in repository environments. General corrosion, localized corrosion, stress corrosion cracking, hydrogen induced cracking, microbially influenced corrosion, and radiation-assisted corrosion of Ti alloys are considered. With respect to the Ti Grade 7 drip shields selected for emplacement in the repository at Yucca Mountain, general corrosion, hydrogen induced cracking, and radiation-assisted corrosion will not lead to failure within the 10,000 year regulatory period; stress corrosion cracking (in the absence of disruptive events) is of no consequence to barrier performance; and localized corrosion and microbially influenced corrosion are not expected to occur. To facilitate the discussion, Ti Grades 2, 5, 7, 9, 11, 12, 16, 17, 18, and 24 are included in this review.

Authors:
; ; ;
Publication Date:
Research Org.:
Yucca Mountain Project, Las Vegas, Nevada (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
837505
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 11 May 2004
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 08 HYDROGEN; 36 MATERIALS SCIENCE; ALLOYS; CORROSION; HYDROGEN; PERFORMANCE; POSITIONING; RADIOACTIVE WASTES; SHIELDS; STRESS CORROSION; TITANIUM ALLOYS; YUCCA MOUNTAIN

Citation Formats

F. Hua, K. Mon, P. Pasupathi, and G. Gordon. A Review Corrosion of TI Grade 7 and Other TI Alloys in Nuclear Waste Repository Environments. United States: N. p., 2004. Web. doi:10.2172/837505.
F. Hua, K. Mon, P. Pasupathi, & G. Gordon. A Review Corrosion of TI Grade 7 and Other TI Alloys in Nuclear Waste Repository Environments. United States. doi:10.2172/837505.
F. Hua, K. Mon, P. Pasupathi, and G. Gordon. Tue . "A Review Corrosion of TI Grade 7 and Other TI Alloys in Nuclear Waste Repository Environments". United States. doi:10.2172/837505. https://www.osti.gov/servlets/purl/837505.
@article{osti_837505,
title = {A Review Corrosion of TI Grade 7 and Other TI Alloys in Nuclear Waste Repository Environments},
author = {F. Hua and K. Mon and P. Pasupathi and G. Gordon},
abstractNote = {Titanium alloy degradation modes are reviewed in relation to their performance in repository environments. General corrosion, localized corrosion, stress corrosion cracking, hydrogen induced cracking, microbially influenced corrosion, and radiation-assisted corrosion of Ti alloys are considered. With respect to the Ti Grade 7 drip shields selected for emplacement in the repository at Yucca Mountain, general corrosion, hydrogen induced cracking, and radiation-assisted corrosion will not lead to failure within the 10,000 year regulatory period; stress corrosion cracking (in the absence of disruptive events) is of no consequence to barrier performance; and localized corrosion and microbially influenced corrosion are not expected to occur. To facilitate the discussion, Ti Grades 2, 5, 7, 9, 11, 12, 16, 17, 18, and 24 are included in this review.},
doi = {10.2172/837505},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue May 11 00:00:00 EDT 2004},
month = {Tue May 11 00:00:00 EDT 2004}
}

Technical Report:

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