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Newman, R.N.; Smith, C.A.; Smith, R.J.
Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.1976
Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.1976
AbstractAbstract
[en] The role of sodium hydroxide corrosion is discussed in relation to the wastage of materials observed in fast reactor boilers under fault conditions in the vicinity of a water leak into sodium. An experimental technique to study the corrosion under varying conditions is described. The results presented are for 2 1/4Cr 1Mo obtained in static sodium hydroxide in a closed volume over the temperature range 1033K to 1273K. It is found that the corrosion rate can be followed by monitoring the hydrogen produced by the reaction, which can be written as: Fe + 2NaOH = NaFeO2 + NaH + 1/2H2. After an initial acceleration period the rate law is parabolic. The effect on the corrosion rate of melt and cover gas composition has been in part investigated, and the relevance of mass flow of reactants is discussed. (author)
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Sep 1976; 21p; ANS conference on liquid metal technology in energy production; Champion, Pennsylvania, USA; 3 - 6 May 1976
Record Type
Report
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Conference
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ALKALI METAL COMPOUNDS, ALLOYS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, ELEMENTS, FLUIDS, HYDROGEN COMPOUNDS, HYDROXIDES, IRON ALLOYS, IRON BASE ALLOYS, KINETICS, METALS, MOLYBDENUM ALLOYS, NONMETALS, OXYGEN COMPOUNDS, REACTION KINETICS, SODIUM COMPOUNDS, STEELS, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENTS
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