A review of degradation behavior of container materials for disposal of high-level nuclear waste in tuff and alternative repository environments
Abstract
Corrosion resistance of materials in aqueous system is reviewed from the perspective of their suitability as container materials for nuclear waste. A discussion of the chemistry and characterization of repository environments, namely, tuff and alternative environments (shale, limestone, and carbonate), is followed by a description of corrosion mechanisms. In this review, emphasis is placed on localized corrosion (e.g., stress corrosion cracking, crevice corrosion, and pitting) because localized corrosion is difficult to account for in design of components, but it is the life-limiting factor for many metallic and nonmetallic systems. The physical metallurgy and microstructure of the potential alloys are briefly described because they provide insight into both the mechanisms of various localized corrosion processes and possible solutions to corrosion problems. A survey of localized corrosion behavior of potential candidate materials as determined by both corrosion and mechanical test in a large number of repository-related environments is presented in order to determine the most promising materials for a given environment. These studies include the effects of various environmental factors (such as pH, temperature, and electrochemical potentials), as well as alloying elements and other microstructural parameters, on corrosion. The modifications of the environment induced by gamma radiation and the stability of themore »
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- OSTI Identifier:
- 137537
- Report Number(s):
- ANL-89/14
ON: DE90000916; TRN: 89:027888
- DOE Contract Number:
- W-31109-ENG-38
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: PBD: Jun 1989
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 05 NUCLEAR FUELS; 36 MATERIALS SCIENCE; 54 ENVIRONMENTAL SCIENCES; 22 NUCLEAR REACTOR TECHNOLOGY; YUCCA MOUNTAIN; RADIOACTIVE WASTE DISPOSAL; CONTAINERS; CORROSION; UNDERGROUND DISPOSAL; MATERIALS; TUFF; SANDSTONES; SHALES; CARBONATES; GROUND WATER; GAMMA RADIATION; SERVICE LIFE; COPPER; COPPER ALLOYS; STAINLESS STEELS; METALLURGY; OXIDATION; CRACKING; STRESSES; DECOMPOSITION; Yucca Mountain Project
Citation Formats
Maiya, P S. A review of degradation behavior of container materials for disposal of high-level nuclear waste in tuff and alternative repository environments. United States: N. p., 1989.
Web.
Maiya, P S. A review of degradation behavior of container materials for disposal of high-level nuclear waste in tuff and alternative repository environments. United States.
Maiya, P S. 1989.
"A review of degradation behavior of container materials for disposal of high-level nuclear waste in tuff and alternative repository environments". United States.
@article{osti_137537,
title = {A review of degradation behavior of container materials for disposal of high-level nuclear waste in tuff and alternative repository environments},
author = {Maiya, P S},
abstractNote = {Corrosion resistance of materials in aqueous system is reviewed from the perspective of their suitability as container materials for nuclear waste. A discussion of the chemistry and characterization of repository environments, namely, tuff and alternative environments (shale, limestone, and carbonate), is followed by a description of corrosion mechanisms. In this review, emphasis is placed on localized corrosion (e.g., stress corrosion cracking, crevice corrosion, and pitting) because localized corrosion is difficult to account for in design of components, but it is the life-limiting factor for many metallic and nonmetallic systems. The physical metallurgy and microstructure of the potential alloys are briefly described because they provide insight into both the mechanisms of various localized corrosion processes and possible solutions to corrosion problems. A survey of localized corrosion behavior of potential candidate materials as determined by both corrosion and mechanical test in a large number of repository-related environments is presented in order to determine the most promising materials for a given environment. These studies include the effects of various environmental factors (such as pH, temperature, and electrochemical potentials), as well as alloying elements and other microstructural parameters, on corrosion. The modifications of the environment induced by gamma radiation and the stability of the microstructure under gamma irradiation are also described. Although in the majority of cases the tests and the environments used are severe, they point out that metallic materials are generally more promising than nonmetallic materials (ceramic and polymeric materials). 122 refs., 61 figs., 19 tabs.},
doi = {},
url = {https://www.osti.gov/biblio/137537},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jun 01 00:00:00 EDT 1989},
month = {Thu Jun 01 00:00:00 EDT 1989}
}