The Development of an Experimental Data Base for the Lifetime Predictions of Titanium Nuclear Waste Containers

The Development of an Experimental Data Base for the Lifetime Predictions of Titanium Nuclear Waste Containers

Author: MG. Bailey

Publisher:

Published: 1994

Total Pages: 17

ISBN-13:

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To predict the expected lifetimes of nuclear waste containers under Canadian disposal vault conditions, specific criteria upon which a predictive model can be based must be developed. The anticipated evolution of the corrosion of titanium waste containers is described. Failure is most likely to occur by a combination of crevice corrosion, hydrogen-induced cracking and general corrosion and, for long lifetimes, the duration of crevice corrosion must be limited. The crevice corrosion of Grade-2 and Grade-12 titanium has been studied using a galvanic coupling technique. The propagation of crevice corrosion on the Grade-2 material is dependent on both temperature and oxygen concentration and repassivation occurs once the oxygen is consumed. The propagation of crevice corrosion on the Grade-12 alloy appears almost independent of temperature, and repassivation occurs for T ?73°C even in the presence of copious amounts of oxygen. The implications for predicting the lifetimes of containers under disposal conditions are discussed.


Development of modelling criteria for predicting lifetimes of titanium nuclear waste containers

Development of modelling criteria for predicting lifetimes of titanium nuclear waste containers

Author: D. W. Shoesmith

Publisher:

Published: 1994

Total Pages: 0

ISBN-13:

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Candidate materials for reactor components of candu primary water systems were corrosion tested in pressurized water at 66 degrees c, 149 degrees c and 293 degrees c for periods of about 12 months. phase iv (ph 10 lioh, approximately 200 ppb o2) was complementary to phase i (ph 10 lioh, less than 5 ppb o2), and with the object of identifying any changes in material corrosion performance subsequent to the possibility of a small ingress of air into the candu-phwr primary water system. dissolved oxygen instigated heavy localized corrosion attack on carbon steel and the low alloy steels, particularly at the lower temperatures of exposure. this localized attack on carbon steel was more apparent in lithiated water than in ammoniated water. in high temperature (293 degrees c) water the presence of dissolved oxygen was beneficial to the uniform corrosion resistance of both carbon steel and stainless steels. dissolved oxygen was deleterious to the corrosion performance of monel 400, chromium based surfaces, sn-bronzes and to some extent 17-4 ph steel and nitrided steel surfaces. after long cumulative exposures to high temperature water there was no evidence of stress corrosion cracking in 17-4 ph (h1050) steel, carpenter custom 455 (h1000) steel, titanium alloys and ni-cr-fe alloy steam generator tubing. cracking was observed, however, in cu-be roll pins and in the carpenter custom 455 (h900) steel.


Review of Corrosion Modes for Alloy 22 Regarding Lifetime Expectancy of Nuclear Waste Containers

Review of Corrosion Modes for Alloy 22 Regarding Lifetime Expectancy of Nuclear Waste Containers

Author:

Publisher:

Published: 2002

Total Pages:

ISBN-13:

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Alloy 22 (UNS N06022) was selected to fabricate the corrosion resistant outer barrier of a two-layer waste package container for nuclear waste at the designated repository site in Yucca Mountain in Nevada (USA). A testing program is underway to characterize and quantify three main modes of corrosion that may occur at the site. Current results show that the containers would perform well under general corrosion, localized corrosion and environmentally assisted cracking (EAC). For example, the general corrosion rate is expected to be below 100 nm/year and the container is predicted to be outside the range of potential for localized corrosion and environmentally assisted cracking.