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http://dx.doi.org/10.14773/cst.2013.12.2.085

Dynamic Boric Acid Corrosion of Low Alloy Steel for Reactor Pressure Vessel of PWR using Mockup Test  

Kim, Sung-Woo (Nuclear Materials Development, Korea Atomic Energy Research Institute)
Kim, Hong-Pyo (Nuclear Materials Development, Korea Atomic Energy Research Institute)
Hwang, Seong-Sik (Nuclear Materials Development, Korea Atomic Energy Research Institute)
Publication Information
Corrosion Science and Technology / v.12, no.2, 2013 , pp. 85-92 More about this Journal
Abstract
This work is concerned with an evaluation of dynamic boric acid corrosion (BAC) of low alloy steel for reactor pressure vessel of a pressurized water reactor (PWR). Mockup test method was newly established to investigate dynamic BAC of the low alloy steel under various conditions simulating a primary water leakage incident. The average corrosion rate was measured from the weight loss of the low alloy steel specimen, and the maximum corrosion rate was obtained by the surface profilometry after the mockup test. The corrosion rates increased with the rise of the leakage rate of the primary water containing boric acid, and the presence of oxygen dissolved in the primary water also accelerated the corrosion. From the specimen surface analysis, it was found that typical flow-accelerated corrosion and jet-impingement occurred under two-phase fluid of water droplet and steam environment. The maximum corrosion rate was determined as 5.97 mm/year at the leakage rate of 20 cc/min of the primary water with a saturated content of oxygen within the range of experimental condition of this work.
Keywords
boric acid corrosion; flow-accelerated corrosion; low alloy steel; mockup test; reactor pressure vessel; primary water leakage;
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Times Cited By KSCI : 1  (Citation Analysis)
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1 H. Xu, S. Fyfitch and J. W. Hyres, Proceedings of the $12^{th}$ Int'l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, p. 855, NACE, Houston (2005).
2 A. Roth and J. Hickling, Proceedings of the $13^{th}$ Int'l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, paper no. 29, NACE, Houston (2007).
3 S. Fyfitch and H. Xu, Proceedings of the $13^{th}$ Int'l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, paper no. 70, NACE, Houston (2007).
4 S. W. Kim, D. J. Kim and H. P. Kim, Nucl. Eng. and Tech., 44, 773 (2012).   DOI   ScienceOn
5 J.-H. Park, O. K. Chopra, K. Natesan and W. J. Shack, Boric Acid Corrosion of Light Water Reactor Pressure Vessel Materials, NUREG/CR-6875 (2005).
6 D. A. Jones, Principles and Prevention of Corrosion, $2^{nd}$ ed. p. 31, Prentice Hall, Upper Saddle River (1996).
7 W. H. Bamford and R. D. Rishel, A Review of Cracking Associated with Weld Deposited Cladding in Operating PWR Plants, WCAP-15338-A, Westinghouse (2002).
8 W. H. Bamford and N. A. Palm, Proceedings of the $14^{th}$ Int'l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, p. 1525, NACE, Houston (2009).
9 KINS, Nuclear Power Plant Incident and Failure Report, 2010-2(100225Y3) (2010).
10 J. H. Park, O. K. Chopra, K. Natesan and W. J. Shack, Proceedings of the $12^{th}$ Int'l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, p. 459, NACE, Houston (2005).
11 A. Roth, E. Nowak, M. Widera, U. Ilg, U. Wesseling and R. Zimmer, Proceedings of the $12^{th}$ Int'l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, p. 795, NACE, Houston (2005).