Performance of iron–chromium–aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions
Zhong, Weicheng, Mouche, Peter A., Han, Xiaochun, Heuser, Brent J., Mandapaka, Kiran K., Was, Gary S.
Published in Journal of nuclear materials (01.03.2016)
Published in Journal of nuclear materials (01.03.2016)
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Nodular corrosion of zirconium alloys in gaseous environment containing different contaminants
Nouduru, Sai Karthik, Mandapaka, Kiran K., Roychowdhury, S., Gumma, Saradhi, Sharma, Rishi, Verma, Rajesh, Kain, Vivekanand
Published in Journal of nuclear materials (01.03.2021)
Published in Journal of nuclear materials (01.03.2021)
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TEM/STEM study of Zircaloy-2 with protective FeAl(Cr) layers under simulated BWR environment and high-temperature steam exposure
Park, Donghee, Mouche, Peter A., Zhong, Weicheng, Mandapaka, Kiran K., Was, Gary S., Heuser, Brent J.
Published in Journal of nuclear materials (15.04.2018)
Published in Journal of nuclear materials (15.04.2018)
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Corrosion behavior of ceramic-coated ZIRLO™ exposed to supercritical water
Mandapaka, Kiran K., Cahyadi, Rico S., Yalisove, Steven, Kuang, Wenjun, Sickafus, K., Patel, Maulik K, Was, Gary S.
Published in Journal of nuclear materials (01.01.2018)
Published in Journal of nuclear materials (01.01.2018)
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Uniform oxidation in steam and nodular corrosion in gas phase of Zr-2.5Nb pressure tube material - effect of nature of initial oxide
Nouduru, Sai Karthik, Mandapaka, Kiran K., Dubey, Vivekanand, Roychowdhury, S., Kain, Vivekanand
Published in Journal of nuclear materials (15.12.2022)
Published in Journal of nuclear materials (15.12.2022)
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Oxidation behavior of Zr-2.5Nb alloy exposed to steam in the temperature range of 600–1200 °C
Krishna, V.S.V. Anantha, Nouduru, Sai Karthik, Mandapaka, Kiran K., Ahmedabadi, Parag M., Abraham, Geogy J., Shukla, S., Roychowdhury, S., Kain, V.
Published in Journal of nuclear materials (15.04.2024)
Published in Journal of nuclear materials (15.04.2024)
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Journal Article
TEM/STEM study of Zircaloy-2 with protective FeAl(Cr) layers under simulated BWR environment and high-temperature steam exposure
Park, Donghee, Mouche, Peter A., Zhong, Weicheng, Mandapaka, Kiran K., Was, Gary S., Heuser, Brent J.
Published in Journal of nuclear materials (01.04.2018)
Published in Journal of nuclear materials (01.04.2018)
Get full text
Journal Article