Sensitivity of measured steam oxidation kinetics to atmospheric control and impurities

E. Sooby Wood; K. A. Terrani; A. T. Nelson

doi:10.1016/j.jnucmat.2016.05.023

Sensitivity of measured steam oxidation kinetics to atmospheric control and impurities

E. Sooby Wood, K. A. Terrani, A. T. Nelson

Research output: Contribution to journal › Article › peer-review

12 Scopus citations

Abstract

The most direct means of improving the ability of water cooled reactors to withstand excessive cladding oxidation during a loss of coolant accident is to either modify or replace zirconium cladding. It is important to understand what level of agreement is to be expected as a function of systematic differences in steam oxidation testing techniques and instrumentation among testing facilities. The present study was designed to assess the sensitivities of some of the current and proposed reactor cladding materials. Steam oxidation sensitivity of Zircaloy-2, FeCrAl and Mo to O₂ impurities in steam were examined. It was shown that the effect of O₂ impurities is negligible for the two former materials while significant in the case of Mo.

Original language	English
Pages (from-to)	228-233
Number of pages	6
Journal	Journal of Nuclear Materials
Volume	477
DOIs	https://doi.org/10.1016/j.jnucmat.2016.05.023
State	Published - Aug 15 2016
Externally published	Yes

Funding

This work was supported by the U.S. Department of Energy, Office of Nuclear Energy Fuel Cycle Research and Development program .

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10.1016/j.jnucmat.2016.05.023

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abstract = "The most direct means of improving the ability of water cooled reactors to withstand excessive cladding oxidation during a loss of coolant accident is to either modify or replace zirconium cladding. It is important to understand what level of agreement is to be expected as a function of systematic differences in steam oxidation testing techniques and instrumentation among testing facilities. The present study was designed to assess the sensitivities of some of the current and proposed reactor cladding materials. Steam oxidation sensitivity of Zircaloy-2, FeCrAl and Mo to O2 impurities in steam were examined. It was shown that the effect of O2 impurities is negligible for the two former materials while significant in the case of Mo.",

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AU - Terrani, K. A.

AU - Nelson, A. T.

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AB - The most direct means of improving the ability of water cooled reactors to withstand excessive cladding oxidation during a loss of coolant accident is to either modify or replace zirconium cladding. It is important to understand what level of agreement is to be expected as a function of systematic differences in steam oxidation testing techniques and instrumentation among testing facilities. The present study was designed to assess the sensitivities of some of the current and proposed reactor cladding materials. Steam oxidation sensitivity of Zircaloy-2, FeCrAl and Mo to O2 impurities in steam were examined. It was shown that the effect of O2 impurities is negligible for the two former materials while significant in the case of Mo.

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ER -

Sensitivity of measured steam oxidation kinetics to atmospheric control and impurities

Abstract

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