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Irradiation Growth of Zirconium Alloys Pages: 8 Published: Jan 1994
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View License Agreement Source: STP1175-EB Abstract Experimental investigation of irradiation growth on annealed Zircaloy-4 and 20% to 50% cold-worked Zr-2.5wt%Nb specimens with stress relief has been carried out. The specimens are irradiated in a heavy water reactor at 610 K to 4.2 x 1024 n/m2 (E > 1.0 MeV). The growth strains increase linearly with fluence. The saturation of growth is not observed for all specimens. The difference of growth behavior between two kinds of Zircaloy-4 tube may be associated with the content of minor alloying elements and impurities that influence the microstructure evolution under irradiation. The difference of growth strains of cold-worked Zr-2.5wt%Nb at different temperature of stress relief is related to the grain size and shape and the degree of cold work. Keywords: zircaloy, irradiation, irradiation growth, texture, neutron fluence, stress relief Paper ID: STP23994S Committee/Subcommittee: E10.02 DOI: 10.1520/STP23994S ASTM International is a member of CrossRef. | ||