journal article·2009-10

Microstructural analysis of MTR fuel plates damaged by a coolant flow blockage

A. Leenaers, F. Joppen, S. Van den Berghe

Journal of Nuclear Materials· Volume 394· Issue 1
Publisher page

Abstract

Abstract In 1975, as a result of a blockage of the coolant inlet flow, two plates of a fuel element of the BR2 reactor of the Belgian Nuclear Research Centre (SCK•CEN) were partially melted. The fuel element consisted of Al-clad plates with 90% 235 U enriched UAl x fuel dispersed in an Al matrix. The element had accumulated a burn up of 21% 235 U before it was removed from the reactor. Recently, the damaged fuel plates were sent to the hot laboratory for detailed PIE. Microstructural changes and associated temperature markers were used to identify several stages in the progression to fuel melting. It was found that the temperature in the center of the fuel plate had increased above 900–950 °C before the reactor was scrammed. In view of the limited availability of such datasets, the results of this microstructural analysis provide valuable input in the analysis of accident scenarios for research reactors.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Heat transfer and supercritical fluids

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References (26)

Show source-provided references
1. Lu · Nucl. Eng. Des. · 2009 · 239 · 4510.1016/j.nucengdes.2008.06.016 ↗
2. Adorni · Ann. Nucl. Energy · 2005 · 32 · 167910.1016/j.anucene.2005.06.001 ↗
3. Adorni · 2007
4. J.E. Matos, in: The Proceedings of the US/IAEA Regional Workshop on Application of the Code of Conduct on the Safety of Research Reactors, Argonne National Laboratory, 2007.
5. Ducros · Nucl. Eng. Des. · 2001 · 208 · 19110.1016/S0029-5493(01)00376-4 ↗
6. Von der Hardt · Nucl. Saf. · 1994 · 35
7. Lewis · J. Nucl. Mater. · 2008 · 380 · 12610.1016/j.jnucmat.2008.07.005 ↗
8. P.G. Ellison, P.R. Monson, M.L. Hyder, in: The Proceedings of the 27th ASME/AICHE/ANS National Heat Transfer Conference, Minneapolis, US, 1991.
9. Buddery · J. Nucl. Mater. · 1961 · 5 · 8110.1016/0022-3115(62)90040-5 ↗
10. Yanagisawa · J. Nucl. Sci. Technol. · 1992 · 29 · 23310.3327/jnst.29.233 ↗
11. Mendoza · Nucl. Technol. · 1981 · 53 · 15510.13182/NT81-A32620 ↗
12. IAEA, Safety Reports Series No. 53, 2008.
13. F. Joppen in: The Proceedings of the 9th International Topical Meeting on Research Reactor Fuel Management (RRFM), Budapest, Hungary, 2005.
14. D. Stahl, ANL-83-5, 1982.
15. Kassner · J. Nucl. Mater. · 1989 · 167 · 16010.1016/0022-3115(89)90438-8 ↗
16. Tougait · Intermetallics · 2004 · 12 · 21910.1016/j.intermet.2003.09.012 ↗
17. A.E. Dwight, Argonne National Laboratory Report No. ANL-82-14, Argonne, IL, 1982.
18. Leenaers · J. Nucl. Mater. · 2008 · 375 · 24310.1016/j.jnucmat.2008.01.013 ↗
19. J. Rest, in: The Proceedings of the 23rd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Las Vegas, Nevada, USA, 2000.
20. Van den Berghe · J. Nucl. Mater. · 2008 · 375 · 34010.1016/j.jnucmat.2007.12.006 ↗
21. T. Shibata, K. Kanda, K. Mishima, T. Tamai, M. Hayashi, J. L. Snelgrove, D. Stahl, J.E. Matos, F.N. Case, J.C. Posey, in: The Proceedings of the International Meeting on Research and Test Reactor Core Conversions from HEU to LEU Fuels, ANL, 1982.
22. NUREG-1313, 1988.
23. Beeston · Nucl. Technol. · 1980 · 49 · 13610.13182/NT80-A32515 ↗
24. Taleyarkhan · Nucl. Saf. · 1992 · 33
25. Zenou · J Alloys Compd. · 2001 · 32910.1016/S0925-8388(01)01675-9 ↗
26. Epstein · Nucl. Eng. Des. · 2000 · 201 · 7110.1016/S0029-5493(00)00263-6 ↗