Effect of Zirconium Hydrides on the mechanical behavior of cladding
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M. A. Martín-Rengel
, F. J. Gomez and J. Ruiz-Hervias
Abstract
During some operations previous to the dry storage, which involve high temperature and hoop stress on the cladding, a part of the hydride platelets may precipitate along the radial direction. As a consequence, cladding embrittlement may occur. In this paper, the experimental techniques developed for the authors to produce hydride reorientation in unirradiated cladding are shown. Samples of fuel cladding with 150 and 500 ppm of hydrogen were prepared. Subsequently, these samples were subjected to reorientation treatments by applying high temperature (400 °C) and constant hoop stress (60, 90, 120 and 140 MPa). Finally, ring compression tests (RCT) were carried out to study the cladding embrittlement. Samples after the reorientation treatment (i.e. with radial hydrides) were subjected to RCT at 20, 135 and 300 °C and the results are discussed.
Kurzfassung
Bei einigen Vorgängen vor der Trockenlagerung, die mit hohen Temperaturen und hoher Ringspannung der Hüllrohre verbunden sind, kann ein Teil der Hydridhüllrohre in radialer Richtung ausfallen. Infolgedessen kann es zu einer Versprödung des Hüllrohrmaterials kommen. In diesem Beitrag werden die experimentellen Techniken gezeigt, die entwickelt wurden, um eine Neuausrichtung des Hydrids in unbestrahlten Hüllrohren zu erreichen. Proben der Brennstoffummantelung mit 150 und 500 ppm Wasserstoff wurden vorbereitet. Anschließend wurden diese Proben einer Neuausrichtung unterzogen, indem eine hohe Temperatur von 400 °C und verschiedene konstante Ringspannungen (60, 90, 120 und 140 MPa) aufgebracht wurden. Schließlich wurden Ringdruckversuche (RCT) durchgeführt, um die Versprödung der Hüllrohre zu untersuchen. Proben nach der Neuorientierungsbehandlung (d.h. mit radialen Hydriden) wurden bei 20, 135 und 300°C einer RCT unterzogen und die Ergebnisse werden in diesem Beitrag diskutiert.
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© 2018, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Editorial
- Safety of extended dry storage of spent nuclear fuel – GRS workshop 2018
- Technical Contributions/Fachbeiträge
- CIEMAT response to challenges on fuel safety research during dry storage
- Research activities at GRS on fuel rod behaviour during extended dry storage
- Open questions on the road to reliable predictions of cladding integrity
- Considerations on spent fuel behavior for transport after extended storage
- Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
- Effect of Zirconium Hydrides on the mechanical behavior of cladding
- Response of irradiated nuclear fuel rods to quasi-static and dynamic loads
- Investigations on potential methods for the long-term monitoring of the state of fuel elements in dry storage casks
Articles in the same Issue
- Contents/Inhalt
- Contents
- Editorial
- Safety of extended dry storage of spent nuclear fuel – GRS workshop 2018
- Technical Contributions/Fachbeiträge
- CIEMAT response to challenges on fuel safety research during dry storage
- Research activities at GRS on fuel rod behaviour during extended dry storage
- Open questions on the road to reliable predictions of cladding integrity
- Considerations on spent fuel behavior for transport after extended storage
- Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
- Effect of Zirconium Hydrides on the mechanical behavior of cladding
- Response of irradiated nuclear fuel rods to quasi-static and dynamic loads
- Investigations on potential methods for the long-term monitoring of the state of fuel elements in dry storage casks