Response of irradiated nuclear fuel rods to quasi-static and dynamic loads
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E. Vlassopoulos
, R. Nasyrow , D. Papaioannou , R. Gretter , L. Fongaro , J. Somers , V. V. Rondinella , S. Caruso , P. Grünberg , J. Helfenstein , P. Schwizer and A. Pautz
Abstract
This paper presents the methodology applied for the experimental and numerical investigation of the mechanical response of spent nuclear fuel rods under static and dynamic loads. The experimental activities were conducted at the JRC Karlsruhe where a 3-point bending test device and an impact tower have been developed and commissioned at the hot-cell facilities. Results are provided for two PWR samples. Load-displacement curves describe the mechanical response of the sample in the 3point bending tests, whereas an image analysis methodology has been developed to comprehend the sample's behaviour under dynamic loads (recorded using a high-speed camera). Finite Element Analysis (FEA) are used to simulate the rod's response based on static and transient structural models in ANSYS Mechanical.
Kurzfassung
Diese Arbeit stellt die angewandte Methodik für die experimentellen und numerischen Untersuchungen hinsichtlich des mechanischen Verhaltens abgebrannter Kernbrennstäbe unter statischen und dynamischen Belastungen vor. Die experimentellen Arbeiten wurden bei der JRC Karlsruhe durchgeführt. Ein 3-Punkt-Biegeprüfgerät und ein Schlagtest-Vorrichtung wurden entwickelt und in den Heissen Zellen in Betrieb genommen. Die Ergebnisse bezüglich zweier DWR-Brennstabproben sind hier dargestellt. Die gemessenen Last-Weg-Kurven beschreiben das mechanische Verhalten der Probe in den 3-Punkt-Biegeversuchen. Zudem wurde eine Bildanalyse-Methode unter Verwendung einer Hochgeschwindigkeitskamera entwickelt, um das Verhalten der Probe unter dynamischen Belastungen zu erfassen. Finite-Elemente-Analysen (FEA) basierend auf statischen und transienten Strukturmodellen in ANSYS-Mechanical werden verwendet, um das Brennstabverhalten unter Lastbedingungen simulieren zu können.
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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