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Open questions on the road to reliable predictions of cladding integrity

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Published/Copyright: January 23, 2019
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Kerntechnik
From the journal Kerntechnik Volume 83 Issue 6

Abstract

The paper at hands discusses the development of an integrated method to predict the fuel rod behavior of LWR-fuel during extended dry storage scenarios. It is well known that degradation effects exist under certain circumstances and that a fuel rod integrity assessment for long-term storage, handling and transport must take these effects into account. It will be elaborated why a complete coverage of the whole lifetime of the fuel rod is necessary. This includes the fabrication, reactor operation, wet storage, drying process, and the dry storage itself. Regarding this approach, a discussion on open questions and challenges will be given.

Kurzfassung

Im vorliegenden Beitrag wird die Entwicklung einer integrierten Methode zur Vorhersage des Brennstabverhaltens von LWR-Brennstoffen während verlängerten Zeiträumen der trockenen Zwischenlagerung diskutiert. Es ist bekannt, dass unter bestimmten Umständen Degradierungseffekte auftreten und dass eine Bewertung der Brennstabintegrität für die langfristige Lagerung, Handhabung und Transport diese Auswirkungen berücksichtigen muss. Es wird erläutert, weshalb eine vollständige Abdeckung der gesamten Lebensdauer des Brennstabs erforderlich ist. Dies schließt die Herstellung, den Einsatz im Reaktor, die Nasslagerung, den Trocknungsprozess und die Trockenlagerung selbst ein. Zu diesem Ansatz wird eine Diskussion über offene Fragen und Herausforderungen geführt.

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References

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Received: 2019-09-11
Published Online: 2019-01-23
Published in Print: 2018-12-17

© 2018, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Editorial
  4. Safety of extended dry storage of spent nuclear fuel – GRS workshop 2018
  5. Technical Contributions/Fachbeiträge
  6. CIEMAT response to challenges on fuel safety research during dry storage
  7. Research activities at GRS on fuel rod behaviour during extended dry storage
  8. Open questions on the road to reliable predictions of cladding integrity
  9. Considerations on spent fuel behavior for transport after extended storage
  10. Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
  11. Effect of Zirconium Hydrides on the mechanical behavior of cladding
  12. Response of irradiated nuclear fuel rods to quasi-static and dynamic loads
  13. Investigations on potential methods for the long-term monitoring of the state of fuel elements in dry storage casks
https://doi.org/10.3139/124.110952

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Editorial
  4. Safety of extended dry storage of spent nuclear fuel – GRS workshop 2018
  5. Technical Contributions/Fachbeiträge
  6. CIEMAT response to challenges on fuel safety research during dry storage
  7. Research activities at GRS on fuel rod behaviour during extended dry storage
  8. Open questions on the road to reliable predictions of cladding integrity
  9. Considerations on spent fuel behavior for transport after extended storage
  10. Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
  11. Effect of Zirconium Hydrides on the mechanical behavior of cladding
  12. Response of irradiated nuclear fuel rods to quasi-static and dynamic loads
  13. Investigations on potential methods for the long-term monitoring of the state of fuel elements in dry storage casks
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