Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Farmer, J.C.; Konynenburg, R.A. Van; McCright, R.D.; Bullen, D.B.

doi:10.2172/7025042

Cited by 7 publications

(25 citation statements)

References 26 publications

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“…Lower temperature sensitization (LTS, ~400 o C) observed over longer periods of time could also be problematic, possibly for 304L and 316L, although high-nickel alloys may not be subject to LTS. However, there was no experimental evidence of a reduction in corrosion resistance due to LTS at the time of the degradation mode surveys of Farmer et al (1988a).…”

Section: Review Of Degradation Mode Surveysmentioning

confidence: 98%

“…Farmer et al, 1988a,b, Gdowski et al, 1988a for waste package candidate materials to be used at Yucca Mountain, including three austenitic alloys (304L, 316L and Alloy 825) and three copper alloys (CDA 102, CDA 613 and CDA 715) used in the nuclear industry and marine environments, respectively. The work contains information on phase stability, environmental effects of a repository, general corrosion, localized corrosion, stress corrosion cracking, hydride cracking, microbially-influenced corrosion and internal corrosion of candidate high-level radioactive waste (HLRW) package materials.…”

Section: Review Of Degradation Mode Surveysmentioning

confidence: 99%

“…In this appendix, we briefly summarize the results of a survey study performed in 1988 (Farmer et al, 1988a) for candidate materials considered for the conceptual design (CD) of the HLRW containers of the YMP Site Characterization Plan (SCP).…”

Section: Appendix Amentioning

confidence: 99%

“…Three austenitic alloys (304 L, 316 L and Alloy 825) and three copper alloys (CDA 102, CDA613 and CDA715) were selected in the 1988 survey (Farmer et al, 1988a), see Table A1a and Table A1b, respectively. The 3 austenitic alloys are used in the nuclear industry.…”

Section: Candidate Materialsmentioning

confidence: 99%

“…The three copper alloys are used in marine environments. Table A1a: Chemical composition of austenitic candidate alloys (Farmer et al, 1988a). Table A1b: Chemical composition of Cu-based candidate alloys (Farmer et al, 1988a).…”

Section: Candidate Materialsmentioning

confidence: 99%

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Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.

Rutqvist¹,

Liu²,

Steefel³

et al. 2011

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Eric Sonnenthal (LBNL) Engineered Barrier System (EBS) Evaluation This page is intentionally left blank Engineered Barrier System (EBS) Evaluation 5 Executive SummaryKey components of the nuclear fuel cycle are short-term storage and long-term disposal of nuclear waste. The latter encompasses the immobilization of used nuclear fuel (UNF) and radioactive waste streams generated by various phases of the nuclear fuel cycle, and the safe and permanent disposition of these waste forms in geological repository environments. The engineered barrier system (EBS) plays a very important role in the long-term isolation of nuclear waste in geological repository environments. EBS concepts and their interactions with the natural barrier are inherently important to the long-term performance assessment of the safety case where nuclear waste disposition needs to be evaluated for time periods of up to one million years. Making the safety case needed in the decision-making process for the recommendation and the eventual embracement of a disposal system concept requires a multi-faceted integration of knowledge and evidence-gathering to demonstrate the required confidence level in a deep geological disposal site and to evaluate longterm repository performance.The focus of this report is the following:• Evaluation of EBS in long-term disposal systems in deep geologic environments with emphasis on the multi-barrier concept;• Evaluation of key parameters in the characterization of EBS performance;• Identification of key knowledge gaps and uncertainties;• Evaluation of tools and modeling approaches for EBS processes and performance.The above topics will be evaluated through the analysis of the following:• Overview of EBS concepts for various NW disposal systems;• Natural and man-made analogs, room chemistry, hydrochemistry of deep subsurface environments, and EBS material stability in near-field environments;• Reactive Transport and Coupled Thermal-Hydrological-Mechanical-Chemical (THMC) processes in EBS;• Thermal analysis toolkit, metallic barrier degradation mode survey, and development of a Disposal Systems Evaluation Framework (DSEF).This report will focus on the multi-barrier concept of EBS and variants of this type which in essence is the most adopted concept by various repository programs. Empasis is given mainly to the evaluation of EBS materials and processes through the analysis of published studies in the scientific literature of past and existing repository research programs. Tool evaluations are also emphasized, particularly on THCM processes and chemical equilibria. Although being an increasingly important aspect of NW disposition, short-term or interim storage of NW will be briefly discussed but not to the extent of the EBS issues relevant to disposal systems in deep geologic environments. Interim storage will be discussed in the report Evaluation of Storage Concepts FY10 Final Report (Weiner et al. 2010). Engineered Barrier System (EBS) Evaluation 6This page is intentionally left blank Engineered Barrier System (EBS) Eva...

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Section: Review Of Degradation Mode Surveysmentioning

confidence: 98%

Section: Review Of Degradation Mode Surveysmentioning

confidence: 99%

Section: Appendix Amentioning

confidence: 99%

Section: Candidate Materialsmentioning

confidence: 99%

Section: Candidate Materialsmentioning

confidence: 99%

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Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.

Rutqvist¹,

Liu²,

Steefel³

et al. 2011

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Localized Corrosion and Stress Corrosion Cracking of Candidate Materials for High-Level Radioactive Waste Disposal Containers in U.S.: A Critical Literature Review

Farmer

McCright

1988

MRS Proc.

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Three iron-based to nickel-based austenitic alloys and three copper-based alloys are being considered in the United States of America as candidate materials for the fabrication of high-level radioactive waste containers. The austenitic alloys are Types 304L and 316L stainless steels as well as the high-nickel material Alloy 825. The copper-based alloys are CDA 102 (oxygen-free copper), CDA 613 (Cu-7A1), and CDA 715 (Cu-30Ni). Waste in the forms of spent fuel assemblies from reactors and borosilicate glass will be sent to a proposed repository at Yucca Mountain, Nevada. The decay of radionuclides will result in the generation of substantial heat and in gamma radiation.Container materials may undergo any of several modes of degradation in this environment, including: undesirable phase transformations due to a lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This paper is an analysis of data from the literature relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of these alloys.Though all three austenitic candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these forms of localized attack. Both Types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented for Alloy 825 under comparable conditions. Gamma irradiation has been found to enhance SCC of Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while microbiologically induced corrosion effects have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems.Of the copper-based alloys, CDA 715 has the best overall resistance to localized attack. Its resistance to pitting is comparable to that of CDA 102 and superior to that of CDA 613; its resistance to crevice corrosion is comparable to that of CDA 613 and superior to that of CDA 102. Observed rates of dealloying in CDA 715 are less than those observed in CDA 613 by orders of magnitude. The resistance of CDA 715 to SCC in tarnishing ammonical environments is comparable to that of CDA 102 and superior to that of CDA 613. Its resistance to SCC in nontarnishing ammonical environments is comparable to that of CDA 613 and superior to that of CDA 102.

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Container Materials for High-Level Nuclear Waste at the Proposed Yucca Mountain Site

McCright

1990

MRS Proc.

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Candidate container materials for high-level nuclear waste packages to be emplaced at the proposed Yucca Mountain repository site are being considered for their long-term resistance to corrosion, oxidation, embrittlement and other kinds of degradation. Selection criteria have been established, and a method has been developed for recommending a material for advanced container design activities. An extensive compilation of the degradation phenomena for six candidate materials is complete, and further studies have begun on the degradation modes affecting additional candidate materials. Phenomenological models for predicting container degradation rates are being advanced for environmental conditions applicable to Yucca Mountain. An experimental program is underway to evaluate the susceptibility of container materials to localized corrosion, stress corrosion cracking, and enhancement of corrosion and oxidation attack by gamma radiation. Initial evaluations of container fabrication and welding processes have identified some processes that appear to alleviate some long-term corrosion susceptibility concerns.

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Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Cited by 7 publications

References 26 publications

Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.

Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.

Localized Corrosion and Stress Corrosion Cracking of Candidate Materials for High-Level Radioactive Waste Disposal Containers in U.S.: A Critical Literature Review

Container Materials for High-Level Nuclear Waste at the Proposed Yucca Mountain Site

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