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Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
2004 International RERTR Meeting

CORROSION OF SPENT NUCLEAR FUEL ALUMINIUM CLADDING IN ORDINARY WATER

M. Pešić, T. Maksin, G. Jordanov, R. Dobrijević
VINČA Institute of Nuclear Sciences
P. O. Box 522, 11001 Belgrade, Serbia and Montenegro
 


ABSTRACT
 

Corrosion of aluminium alloy cladding of spent nuclear fuel elements in ordinary water is examined in the spent fuel storage pool of the RA research reactor at the Vinča Institute of Nuclear Sciences, Belgrade, Serbia and Montenegro. Experimental examinations are carried out within framework of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) “Corrosion of Research Reactor Aluminium-Clad Spent Fuel in Water”, Phase II. Racks with coupons made of different aluminium alloys were exposed to water influence for period of six months to six years. The project comprises also activities on monitoring of the water chemistry and radioactivity in the storage pool. Visual and microscopic examinations of surfaces of aluminium coupons of the test racks have been done recently and results were presented in this paper confirming strong influence of water quality and exposition time to corrosion process.


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2016 RERTR Meeting

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Last modified on July 29, 2008 11:32 +0200