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AbstractAbstract
[en] In the CORECT II facility a series of experiments concerning the thermal interaction between molten UO/sub 2/ (fuel) and liquid sodium (coolant) have been performed. The test which has provided the most significant results from the point of view of the resulting mechanical effects (pressure in the interaction zone, mechanical energy) involves 5 kg of molten UO/sub 2/ and sodium at 700/degree/C. This paper presents the results of this test and their interpretation as obtained with the MURTI code. 1 ref
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Source
Anon; p. 1512-1519; 1979; p. 1512-1519; American Nuclear Society; LaGrange Park, IL; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979
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Book
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Conference
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