SYMPOSIA PAPER Published: 01 February 2018
STP159720160085

Neutron Irradiation Effects on the Corrosion of Zircaloy-4 in a Pressurized Water Reactor Environment

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Long-time Advanced Test Reactor (ATR) corrosion weight-gain data from nonfueled α-processed Zircaloy-4 cladding coupons are presented herein. The data were generated in pressurized loops that simulated pressurized water reactor (PWR) chemistry, temperature, and neutron flux conditions. High neutron flux and high-fluence post-transition corrosion rates were accelerated over out-of-flux post-transition corrosion rates by more than 40 times at 270°C and more than 30 times at 310°C. We conclude in large part that the acceleration was caused by irradiation-induced changes to the base metal. The effect that irradiation has on the base metal and its effect on corrosion has been shown in the past to be carried over into post-irradiation tests in autoclave environments, but its impact was shown in this study to be accentuated in the in-reactor environment, in which sustained corrosion accelerations were much greater than observed in the postirradiation tests (in nonirradiation environments). This suggests some aspect of the radiation environment potentially acts synergistically with the corrosion film formed from the irradiation-damaged base metal to further accelerate in-reactor corrosion rates. We also present results from detailed microstructural examinations of thick (more than 25 µm) oxide films formed on α-processed Zircaloy-4 grown in a 360°C autoclave and in the reactor. The examinations consisted of optical microscopy, field emission gun scanning electron microscopy, focused ion beam microscopy, analytical electron microscopy, and X-ray diffraction, with a focus on the evolution of the microstructure of the intermetallic precipitates in the oxide films during exposure to autoclave water or to the corroding environment under neutron irradiation. The film microstructure suggests that the water environment was closer to the oxide-metal interface in the films grown in the reactor than in the autoclave-grown corrosion films examined, but it was not obvious from the microstructural examinations how the radiation environment facilitated that effect.

Author Information

Kammenzind, Bruce, F.
Bechtel Marine Propulsion Corporation, Bettis Laboratory, West Mifflin, PA, US
Gruber, Jason, A.
Bechtel Marine Propulsion Corporation, Bettis Laboratory, West Mifflin, PA, US
Bajaj, Ram
Bechtel Marine Propulsion Corporation, Bettis Laboratory, West Mifflin, PA, US
Smee, James, D.
Bechtel Marine Propulsion Corporation, Bettis Laboratory, West Mifflin, PA, US
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Details
Developed by Committee: B10
Pages: 448–490
DOI: 10.1520/STP159720160085
ISBN-EB: 978-0-8031-7642-3
ISBN-13: 978-0-8031-7641-6