SYMPOSIA PAPER Published: 01 January 2000
STP14322S

The Effect of Microstructure on the Corrosion Behavior of Zircaloy-2 in BWRs

Source

For improved Zircaloy-2 cladding tubes used in Japanese BWRs, α+β heat treatment is used on the outer surface of the tubeshell to suppress nodular corrosion. This treatment also provides superior uniform corrosion behavior up to 40 GWd/t. To investigate the effect of α+β heat treatment on corrosion behavior, the size distributions of second-phase particles in improved Zircaloy-2 cladding tubes and their changes during irradiation were observed and measured using an analytical transmission electron microscope. These cladding tubes were found to have smaller particles than previous ones. The dissolution rate of iron and nickel (Fe and Ni) was calculated as a function of particle size, chemical compositions of cladding tubes, and fast neutron flux. The relationship between corrosion behavior and the dissolution rate of Fe and Ni is described. Nodular corrosion occurred when the dissolution rate of Fe and Ni was slow.

Author Information

Etoh, Y
Nippon Nuclear Fuel Development Co., Ltd., Ibaraki-ken, Japan
Nonaka, Y
Nippon Nuclear Fuel Development Co., Ltd., Ibaraki-ken, Japan
Kubo, T
Hitachi, Ltd., Ibaraki-ken, Japan
Nomata, T
Toshiba Corp., Kanagawa-ken, Japan
Hayashi, H
Nuclear Power Engineering Corporation, Tokyo, Japan
Kitamura, M
Nuclear Power Engineering Corporation, Tokyo, Japan
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Details
Developed by Committee: B10
Pages: 658–677
DOI: 10.1520/STP14322S
ISBN-EB: 978-0-8031-5416-2
ISBN-13: 978-0-8031-2499-8