Published June 1996 | Version v1
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The effect of heat treatments on the corrosion behavior of Zircaloy-4

  • 1. National Key Lab. for Nuclear Fuel and Materials, Nuclear Power Inst. of China, Chengdu (China)

Description

The effect of penultimate annealing temperature and cooling rate on the corrosion behavior of Zircaloy-4 cladding tube has been investigated. Both nodular corrosion and uniform corrosion resistance can be improved obviously after changing the heat treatment from the original annealing at 650 degree C to quenching from 830 degree C (upper temperature of alpha phase region or lower temperature of beta phase region). Although the nodular corrosion resistance can be improved obviously after quenching from beta phase, there was a second transition in the variation between weight gain and exposure time, which shows a poor uniform corrosion resistance after a long exposure time during the autoclave tests. The main factor of affecting corrosion behavior is the solid solution contents of Fe and Cr in alpha zirconium rather than the size of second phase particles. About 200 μg/g Fe and Cr super saturated solid solution in alpha zirconium could get good uniform and nodular corrosion resistance, but much more solid solution contents of Fe and Cr in alpha zirconium could bring about a trend toward poor uniform corrosion resistance for long-term exposure time. (14 refs., 10 figs., 1 tab.)

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MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
14 p.
Report number
CNIC--01074

Optional Information

Secondary number(s)
SINRE--0066.