SYMPOSIA PAPER Published: 01 January 1994
STP23994S

Irradiation Growth of Zirconium Alloys

Source

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.

Author Information

Yang, JC
China Institute of Atomic Energy, Beijing, China
Ren, JY
China Institute of Atomic Energy, Beijing, China
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Details
Developed by Committee: E10
Pages: 1140–1147
DOI: 10.1520/STP23994S
ISBN-EB: 978-0-8031-5262-5
ISBN-13: 978-0-8031-1488-3