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AbstractAbstract
[en] The investigation on the compatibility between China Experimental Fast Reactor (CEFR) welded specimens with sodium was performed under simulative operation conditions of CEFR. The intergranular corrosion and the variation in mechanical properties were observed and determined after test in 450 degree C sodium for 3000 h. The average corrosion rate is less than 0.9 mg/(m2·h) and the intergranular corrosion is not observed at the welded specimen surface contacted with sodium. Comparing tensile behaviors of as-received specimens with that of corroded specimens, the difference on the yield strength (R0.2%) and ultimate tensile strength (UTS) as well as elongation percent (A%) are not considerable before and after of experiment. (authors)
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6 figs., 1 tab., 4 refs.
Record Type
Journal Article
Journal
Atomic Energy Science and Technology; ISSN 1000-6931; ; v. 40(5); p. 534-538
Country of publication
ALKALI METALS, ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION, CORROSION RESISTANT ALLOYS, DEFORMATION, ELEMENTS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, MATERIALS, MECHANICAL PROPERTIES, METALS, NICKEL ALLOYS, REACTORS, RESEARCH AND TEST REACTORS, STAINLESS STEELS, STEEL-CR19NI10, STEELS, TEMPERATURE RANGE, TRANSITION ELEMENT ALLOYS
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