Hostname: page-component-586b7cd67f-2plfb Total loading time: 0 Render date: 2024-11-28T10:10:56.804Z Has data issue: false hasContentIssue false
  • English
  • Français

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

Published online by Cambridge University Press:  01 February 2011

Mirco Grosse ,
Marius van den Berg ,
Eberhard Helmar Lehmann  and
Burkhard Schillinger
Mirco Grosse
Affiliation:
[email protected], Karlsruhe Institute of Technology, Institute for Materials Research, Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen, D-76344, Germany
Marius van den Berg
Affiliation:
[email protected], Karlsruhe Institute of Technology, Institute for Materials Research, Karlsruhe, Germany
Eberhard Helmar Lehmann
Affiliation:
[email protected], Paul Scherrer Institute, Spallation Neutron Source, Villigen PSI, Switzerland
Burkhard Schillinger
Affiliation:
[email protected], TU Munich, FRM-2, Garching, Germany
Get access

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.

Keywords

neutron scatteringhydrogenationZr
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1262: Symposium V/W – In-Situ and operando Probing of Energy Materials at Multiscale Down to Single Atomic Couumn-The Powerof X-Rays, Neutons and Electrons Microscopy , 2010 , 1262-W03-09
Copyright
Copyright © Materials Research Society 2010

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1 Steinbrück, M., J. Nucl. Mater. 334, 58 (2004).Google Scholar
2 Grosse, M., Steinbrueck, M., Lehmann, E., and Vontobel, P., Oxid. Metals 70, 149 (2008).Google Scholar
3 Stuckert, J., Birchley, J., Grosse, M., Haste, T., Sepold, L., and Steinbrueck, M. M., Annals of Nuclear Energy 36, 183 (2009).Google Scholar
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 12–16, ICONE17-75266.Google Scholar
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.Google Scholar