Abstract
Molybdenum has recently gained attention as a candidate cladding material for use in light water reactors. Its excellent high temperature mechanical properties and stability under irradiation suggest that it could offer benefits to performance under a wide range of reactor conditions, but little is known about its oxidation behavior in water vapor containing atmospheres. The current study was undertaken to elucidate the oxidation behavior of molybdenum in water vapor environments to 1200 °C in order to provide an initial assessment of its feasibility as a light water reactor cladding. Initial observations indicate that at temperatures below 1000 °C, the kinetics of mass loss in water vapor would not be detrimental to cladding integrity during an off-normal event. Above 1000 °C, degradation is more rapid but remains slower than observed for optimized zirconium cladding alloys. The effect of hydrogen-water vapor and oxygen-water vapor mixtures on material loss was also explored at elevated temperatures. Parts-per-million levels of either hydrogen or oxygen will minimally impact performance, but hydrogen contents in excess of 1000 ppm were observed to limit volatilization at 1000 °C.
Original language | English |
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Pages (from-to) | 441-447 |
Number of pages | 7 |
Journal | Journal of Nuclear Materials |
Volume | 448 |
Issue number | 1-3 |
DOIs | |
State | Published - May 2014 |
Externally published | Yes |
Funding
Portions of this work were supported by the U.S. Department of Energy, Office of Nuclear Energy Fuel Cycle Research and Development program. Autoclave corrosion testing has been funded by the Electric Power Research Institute. E.A. Sooby would like to express appreciation to the Seaborg Institute at Los Alamos for supporting her work on this project.
Funders | Funder number |
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U.S. Department of Energy | |
Electric Power Research Institute |