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Ex-situ and in-situ Neutron Radiography Investigations of the Hydrogen Uptake of Nuclear Fuel Cladding Materials During Steam Oxidation at 1000°C and Above

  • Mirco Grosse (a1), Marius van den Berg (a2), Eberhard Helmar Lehmann (a3) and Burkhard Schillinger (a4)

Abstract

Neutron radiography is a powerful tool for the investigation of the hydrogen uptake of zirconium alloys. It is fast, fully quantitative, non-destructive and provides a spatial resolution of 30 μm. The non-destructive character of neutron radiography provides the possibility of in-situ investigations. The paper describes the calibration of the method and delivers results of ex-situ measurements of the hydrogen concentration distribution after steam oxidation, as well as in-situ experiments of hydrogen diffusion in β-Zr and in-situ investigations of the hydrogen uptake during steam oxidation.

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1 Steinbrück, M., J. Nucl. Mater. 334, 58 (2004).
2 Grosse, M., Steinbrueck, M., Lehmann, E., and Vontobel, P., Oxid. Metals 70, 149 (2008).
3 Stuckert, J., Birchley, J., Grosse, M., Haste, T., Sepold, L., and Steinbrueck, M. M., Annals of Nuclear Energy 36, 183 (2009).
4 Stuckert, J., Grosse, M., Sepold, L., and Steinbrueck M., M., (2009), “Experimental results of reflood bundle test Quench-14 with M5® cladding tubes”, Proceedings of the 17th International Conference on Nuclear Engineering (ICONE-17), Bruxelles, B, July 1216, ICONE17-75266.
5 Stuckert, J., Grosse, M., Sepold, L., and Steinbrueck, M.., (2009), “Experimental results of reflood bundle test QUENCH-15 with ZIRLOTM cladding tubes”, Steinbrück, M., (Ed.), Proceedings of the 15th International QUENCH Workshop, Karlsruhe, November 3-5, Karlsruhe Institute of Technology, ISBN 978-3-923704-71-2.

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