INVESTIGATION ON ALLOYS OF ZIRCONIUM WITH NIOBIUM AND/OR SILICON IN VIEW OF THEIR USE AS SHEATHING MATERIAL IN WATER-COOLED NUCLEAR REACTORS. Quarterly Report No. 3.

Author: Anderko, K.
Published: United States : [publisher not identified], 1961.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1961.
Physical Description: microopaque : positive ; 8 x 13 cm
Additional Creators: Jung-Koenig, W., Richter, H., Schleicher, H.-W., and Zwicker, U.

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Summary

Investigation of Zr-- Nb system was resumed and the results of the previous investigation were confirmed. The temperature dependence of the solubility of niobium in the mixed crystal of alpha -zirconium was determined beth with spongy zirconium and iodide zirconium as starting material. On account of the impurities contained in spongy zirconium, the equilibrium temperature of the alloy in the monotectoid range, as well as the BETA / alpha + BETA phase boundary were shifted toward considerably higher temperatures compared to alloys with iodide zirconium as starting material. The martensitic platelets which separate in alloys with niobium contents ranging between 7.5 and 17% of niobium when quenched in water, could be ascribed to the presence of hydrogen. The comparative corrosion tests in water or steam at 360, 400, and 480 deg C respectively, were extended. The first series of 2.000-hour tests at400 deg C and 1.000 h tests at 480 deg C were brought to an end. An investigation on the hydrogen absorption of a few alloys with niobium content during the corrosion process was made and resulted in considerably lower values than those which can be observed with Zircaloy-2. In a new series of tests, binary, ternary and quaternary zirconium alloys with niobium content were subjected to the action of water or steam at 350, 400, and 480 deg C after having been heat-treated for 10 days at 575 deg C or 1 hour at 650 deg C. The results of these experiments after 500 hours show that the heat treatment at 575 deg C is beneficial and thus confirms the opinion which had already arisen, that annealing below the monotectoid range has a particularly favorable influence. The systematic corrosion tests pointed to the fact that alloys with 3% of niobium and 1% of tin were particularly promising. The alloys Zircaloy-2 and ZrNb/sub 2/ intended for the endurance tests when treated at temperatures of 250, 350, and 450 deg C, exhibited permanent elongations after times extending even up to 500 hours. (auth)

Report Numbers

EURAEC-85

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Collection

U.S. Atomic Energy Commission depository collection.

Note

DOE contract number: 009-60-4RDA
NSA number: NSA-16-020982
OSTI Identifier 4816181
Research organization: Metallgesellschaft A.G., Frankfurt am Main.

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INVESTIGATION ON ALLOYS OF ZIRCONIUM WITH NIOBIUM AND/OR SILICON IN VIEW OF THEIR USE AS SHEATHING MATERIAL IN WATER-COOLED NUCLEAR REACTORS. Quarterly Report No. 3.

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