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Hofman, G.L.; Marajofsky, A.; Kohut, C.
Argonne National Lab., IL (USA)1988
Argonne National Lab., IL (USA)1988
AbstractAbstract
[en] Since 1978 the CNEA ECBE project has been involved in the development of dispersion fuel plates with four types of fuel materials -- UAlx, U3O8, U3Si, and U3Si2 -- to be used in low enriched (LEU < 20% 235U) fuel elements for research reactors. Miniplates with these fuel materials were manufactured at CNEA and were irradiated in the ORR in three series of irradiations as part of the RERTR miniplate irradiation program. The first irradiation contained U3O8 and UAlx fuel, the second U3O8, UAlx and U3Si, while the third irradiation test consisted of six U3Si2 miniplates and one U3Si miniplate. This third test is the subject of this paper. The present results compare favorably with other irradiations performed in the RERTR program1,2 showing in particular the excellent behavior of the U3Si2. The overall data accumulated support the qualification of the CNEA fabrication techniques. 5 refs., 13 figs., 3 tabs
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1988; 25 p; International meeting on reduced enrichment for research and test reactors (RERTR); San Diego, CA (USA); 18-24 Sep 1988; CONTRACT W-31109-ENG-38; NTIS, PC A03/MF A01 as DE90003800; OSTI; INIS; US Govt. Printing Office Dep
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Report
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Conference
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ALUMINIUM ALLOYS, BLISTERS, BUBBLES, BURNUP, CLADDING, DATA ACQUISITION, FUEL ELEMENTS, IRRADIATION, MATERIALS TESTING, MEASURING METHODS, METALLOGRAPHY, ORR REACTOR, PERFORMANCE TESTING, PLANNING, PLATES, POROSITY, POST-IRRADIATION EXAMINATION, RECOMMENDATIONS, SPECTROSCOPY, SWELLING, TEMPERATURE DEPENDENCE, URANIUM ALLOYS, URANIUM COMPOUNDS
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