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Fast water flow facilitates ferrous ion transport leading to flow accelerated corrosion (FAC) of carbon steel and the possibility of a large accident through a failure of a secondary pipe in a nuclear power plant. Ion transport is directly linked to oxide properties such as the thickness, chemical composition and porosity. This work deals with a precise observation of the cross section of the corroded specimen focusing on an oxide passivity and its thickness using SEM (scanning electron microscope) and TEM (transmission electron microscope) as well as an apparent weight loss and a surface observation for the specimens corroded using a rotating cylindrical electrode autoclave system in pure water of pH 7 at 150°C having dissolved oxygen below 1 ppb within a flow rate range of 0 to 10 m/s. The Cr content in steel was changed from 0.02 to 2.4 wt%. Increasing the Cr content in the alloy, the FAC rate and oxide thickness decreased. The oxide porosity tends to decrease with the Cr content and immersion time owing to the development of Cr containing oxide. The oxidation behavior is not changed with the immersion time.
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1383--1387
Opis fizyczny
Bibliogr. 10 poz., rys., tab.
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autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
autor
- Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daedeok Daero 989-111, Yuseong, Daejeon, Korea, 34057
Bibliografia
- [1] Flow accelerated corrosion in power plants, EPRI report, TR--106611-R1, Palo Alto, CA, 1998.
- [2] J. Robertson, Corrosion Science 29, 1275 (1989).
- [3] D.J. Kim, H.C. Kwon, H.P. Kim, Corrosion Science 50, 1221 (2008).
- [4] D.J. Kim, H.C. Kwon, H.W. Kim, S.S. Hwang, H.P. Kim, Corrosion Science 53, 1247 (2011).
- [5] S.Y. Kang, D.W. Lee, J. Korean Power Metallurgy Institute, 21, 260 (2014).
- [6] J.-P. Lee, J.-H. Hong, D.-K. Park, I.-S. Ahn, J. Korean Power Metallurgy Institute, 22, 52 (2015).
- [7] L.E. Sanchez-Caldera, P. Griffith, E. Rabinowicz, J. Engineering for Gas Turbines and Power 110, 180 (1988).
- [8] H. Abe, T. Yano, Y. Watanabe, M. Nakashima, T. Tatsuki, presented at FAC 2016, May 24-27, 2016, Lille, France.
- [9] S.I. Pyun, The Fundamentals of Corrosion of Metals and Their Application into Practice, Chungwoongak 2006.
- [10] H.P. Kim, M.J. Kim, D.J. Kim, presented at 19th ICC, Nov. 2-6, 2014, Jeju, Korea.
Uwagi
PL
Opracowanie ze środków MNiSW w ramach umowy 812/P-DUN/2016 na działalność upowszechniającą naukę (zadania 2017)
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-6beddca8-166b-4984-b3f7-1d2eff156353