[en] Metallographic and hydrogen content analysis and autoclave corrosion test for irradiated Zircaloy-4 sample of different heat-treatment show that Zircaloy-4 specimens with water-quench at 1030℃ possesses the best corrosion resistance in the neutron fluence of (4∼7) × 1021 n/cm2, it is accordant with the same rule of non-irradiated specimens with the same heat-treatment. No difference of corrosion weight gain is found on three kinds of specimens with difference heat-treatment effect. The hydride disperse uniformly in three kinds of specimens matrix. There is no obvious distinction of hydrogen content in samples through different heat-treatment. (authors)
Source
Chinese Nuclear Society, Beijing (China); 328 p; ISBN 978-7-5022-5602-9; 
; Oct 2012; p. 34-39; 2011 academic annual meeting of China Nuclear Society; Beijing (China); 11-14 Oct 2011; 6 figs., 3 tabs., 4 refs.
; Oct 2012; p. 34-39; 2011 academic annual meeting of China Nuclear Society; Beijing (China); 11-14 Oct 2011; 6 figs., 3 tabs., 4 refs.