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Efanov, A.D.; Zhukov, A.V.; Kuzina, Ju.A.; Sorokin, A.P.; Smirnov, V.P.; Sila-Novitsky, A.G.
Advisory group meeting on design and performance of reactor and subcritical blanket systems with lead and lead-bismuth as coolant and/or target material. Working material2001
Advisory group meeting on design and performance of reactor and subcritical blanket systems with lead and lead-bismuth as coolant and/or target material. Working material2001
AbstractAbstract
[en] The results of thermal-hydraulic studies for the experimental demonstration lead-cooled fast reactor BREST-OD-300 are considered. Experimental studies of heat transfer coefficients and temperature fields of fuel rods for the BREST type reactors were carried out using three thermalhydraulic models.Simulating coolant used was eutectic alloy sodium-potassium. The fuel tested was uranium or plutonium mononitride, the cladding was stainless steel, the interlayer was lead. Obtained results are shown in detail together with the prospective of future studies
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Source
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); 367 p; 2001; p. 291-306; IAEA-IWGFR advisory group meeting on design and performance of reactor and subcritical blanket systems with lead and lead-bismuth as coolant and/or target material; Moscow (Russian Federation); 23-27 Oct 2000; 4 refs, 19 figs
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACTINIDE COMPOUNDS, ALKALI METALS, ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, ELEMENTS, ENERGY TRANSFER, EPITHERMAL REACTORS, FAST REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MECHANICS, METALS, NITRIDES, NITROGEN COMPOUNDS, PLUTONIUM COMPOUNDS, PNICTIDES, REACTORS, STEELS, TRANSITION ELEMENT ALLOYS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS
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