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AbstractAbstract
[en] Since 1972 INTERATOM is performing sodium mass and activity transfer investigations in an SNR-corrosion mockup loop which allows to study the transport of activated corrosion products in the primary heat transfer system of a sodium cooled reactor. The loop simulates the temperature and flow conditions and the materials combination of the SNR 300. The mass transfer examinations were aimed at the determination of the following: the linear corrosion and deposition rates; the selective corrosion of the alloying elements; the transfer of activated corrosion products. The results of a number of corrosion runs will be used in the following contribution to characterize the contaminated and corroded surface layers of reactor components. The loop reached a total operation time of 12300 h while the cold trap temperature was changed between 105 deg. C and 165 deg. C in successive runs
Primary Subject
Source
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); 213 p; Aug 1978; p. 47-50; IAEA-IWGFR specialists meeting on sodium removal and decontamination; Richland, WA (United States); 14-16 Feb 1978; 5 refs, 2 figs, 1 tab
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALKALI METALS, BREEDER REACTORS, CHEMICAL REACTIONS, COOLING SYSTEMS, ELEMENTS, ENERGY SYSTEMS, ENERGY TRANSFER, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, METALS, POWER REACTORS, REACTORS, SODIUM COOLED REACTORS, TRAPS, VAPOR CONDENSERS
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