Potential corrosion and degradation mechanisms of Zircaloy cladding on spent nuclear fuel in a tuff repository

Rothman, Allison

doi:10.2172/59331

Cited by 30 publications

(27 citation statements)

References 24 publications

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“…A vast amount of testing has been conducted in high-temperature conditions, and several correlations and factors influencing corrosion rate have been obtained and evaluated. Rothman [8] had attempted to predict the Zry corrosion rate in a tuff repository by extrapolating correlations obtained in high-temperature corrosion tests in 1984. Later, Hillner et al [9] analyzed long-term Zry autoclave corrosion data to develop new correlations.…”

Section: Methods To Evaluate Low-temperature Corrosion Based On Knowlementioning

confidence: 99%

Long-Term Corrosion of Zircaloy Hull Waste under Geological Disposal Conditions: Corrosion Correlations, Factors Influencing Corrosion, Corrosion Test Data, and Preliminary Evaluation

Tanabe¹,

Sakuragi²,

Miyakawa³

et al. 2014

MRS Proc.

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The carbon-14 generated in Zircaloy (Zry) hull waste is considered an important radionuclide in the TRU waste geological disposal concept in Japan. Given that the metal Zry is highly corrosion-resistant in the anaerobic and low-temperature conditions of the repository, and that the C-14 release rate is assumed to be controlled by the corrosion rate, a variety of corrosion and leaching tests have been performed. However, since the Zry corrosion rate is extremely slow, it is not possible to predict long-term corrosion behavior through low-temperature corrosion tests conducted in a reasonable time period. A vast amount of testing has been conducted in the higher-temperature range of 523 to 633 K, and corrosion correlations have been obtained from these tests. Corrosion correlations have been used to predict the corrosion rate of Zry in a tuff repository. Long-term Zry autoclave corrosion data have been analyzed to develop new corrosion correlations. Extrapolating these correlations to a lower temperature range requires verification that the mechanisms do not change over the range of testing and extrapolation. Factors that influence corrosion rates under geological disposal conditions, such as material and environmental factors, should also be examined. Corrosion correlations, factors influencing corrosion rates, the results of corrosion and leaching tests, and a preliminary evaluation are discussed.

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Section: Methods To Evaluate Low-temperature Corrosion Based On Knowlementioning

confidence: 99%

Long-Term Corrosion of Zircaloy Hull Waste under Geological Disposal Conditions: Corrosion Correlations, Factors Influencing Corrosion, Corrosion Test Data, and Preliminary Evaluation

Tanabe¹,

Sakuragi²,

Miyakawa³

et al. 2014

MRS Proc.

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“…The information in the Rothman (1984) and Pescatore et al (1990) is probably sufficient for a compliant validation strategy. The abstracted model should be listed as a model and a validation section should be added.…”

Section: Review Findingsmentioning

confidence: 99%

Model Validation Status Review

Hardin¹

2001

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EXECUTIVE SUMMARYThis Model Validation Status Review (MVSR) technical report was prepared as part of the (amended) response to Corrective Action Request BSC-0 1 -D-00 1 (Clark 2001, Krisha 200 1). This report documents a systematic, one-time review of all the Analysis/Model Reports (AMRs) that support the Total System Performance Assessment -Site Recommendation (TSPA-SR), by an independent team under the direction of the Bechtel SAIC Company Chief Science Officer.A total of 125 AMRs plus other documents and data were reviewed. The review team first identified the models documented in the AMRs. Then they determined how the models were used in development of the TSPA-SR. Finally, the models were assigned to three categories ("bins") according to the extent to which model validation was achieved in compliance with Administrative Procedure AP-3.1 OQ, Analyses and Models. Review-team recommendations are provided for improvement of documentation, and in some cases, for fbrther model development, testing, or data collection to improve the models in support of licensing activities.A total of 128 models were identified, of which 17 were assigned to Bin 1 (compliant validation), 77 were assigned to Bin 2 (information readily available for validation but documentation not in compliance), and 34 were assigned to Bin 3 (not in compliance and not readily validated). For the 34 Bin-3 models, impact reviews were conducted and the resulting impact review documentation is summarized in Section 6, and included in Appendix IV to this technical report. For all 34 Bin-3 models, the impact reviews found no significant impact from the model validation review findings, on the conclusions of the TSPA-SR (i.e., the calculated annual dose is negligible). Impact Review Summary for Bin-3 ModelsOf the 34 Bin-3 models, the impact reviews for 24 can be summarized as follows:Sixteen were found not to support TSPA-SR, i.e., the output from these models was not used as input to the system model. All 16 of these models are developmental, and some have been superseded by other products. Of these 16 models, only six were used for screening out of features, events, and processes (FEPs) from the TSPA-SR.Five additional Bin-3 models (not among the 16 discussed above) were originally intended by the authors to be analyses or calculations (i.e., not requiring validation). At the time this work was documented, the authors determined that model validation was not required based on consideration of details such as the analysis methods used and the contribution to TSPA-SR. The review team identified these as models requiring validation, using the criteria from Section 3.4.2 of this report.Three additional Bin-3 models in the Biosphere area were embedded within the GENII-S dose-assessment code and were not previously recognized as discrete models. (The GENII-S code is a widely used and accepted approach, but application to a potential Yucca Mountain geologic repository is not yet hlly documented.)TDR-WIS-MD-000005 REV 00Page vii November 200 1The remaining 10 ...

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“…Cox (1976) has reviewed oxidation characteristics of Zircaloy extensively. Rothman (1984) has evaluated these Zircaloy characteristics further in tuff environments.…”

Section: Perf'ormance Of Cladding Materialsmentioning

confidence: 99%

Dry oxidation and fracture of LWR spent fuels

Ahn¹

1996

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Potential corrosion and degradation mechanisms of Zircaloy cladding on spent nuclear fuel in a tuff repository

Cited by 30 publications

References 24 publications

Long-Term Corrosion of Zircaloy Hull Waste under Geological Disposal Conditions: Corrosion Correlations, Factors Influencing Corrosion, Corrosion Test Data, and Preliminary Evaluation

Long-Term Corrosion of Zircaloy Hull Waste under Geological Disposal Conditions: Corrosion Correlations, Factors Influencing Corrosion, Corrosion Test Data, and Preliminary Evaluation

Model Validation Status Review

Dry oxidation and fracture of LWR spent fuels

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