가압형 경수로 압력용기 재료인 저합금강의 동적 붕산 부식 실증 연구
Dynamic Boric Acid Corrosion of Low Alloy Steel for Reactor Pressure Vessel of PWR using Mockup Test
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초록
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.
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.
참고문헌 (11)
- A Review of Cracking Associated with Weld Deposited Cladding in Operating PWR Plants, "W. H. Bamford", Westinghouse, ~, pp.WCAP-15338-A (2002)
- W. H. Bamford, , Proceedings of the 14th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, pp.1525~ (2009), NACE
- Nuclear Power Plant Incident and Failure Report, "KINS", ~, pp.2010-2(100225Y3) (2010)
- J. H. Park, , Proceedings of the 12th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, pp.459~ (2005), NACE
- A. Roth, , Proceedings of the 12th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, pp.795~ (2005), NACE
- H. Xu, , Proceedings of the 12th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, pp.855~ (2005), NACE
- A. Roth, , Proceedings of the 13th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 29 (2007), NACE
- S. Fyfitch, , Proceedings of the 13th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 70 (2007), NACE
- Sung-Woo Kim, "EVALUATION OF GALVANIC CORROSION BEHAVIOR OF SA- 508 LOW ALLOY STEEL AND TYPE 309L STAINLESS STEEL CLADDING OF REACTOR PRESSURE VESSEL UNDER SIMULATED PRIMARY WATER ENVIRONMENT", Nuclear Engineering and Technology, 44(7), pp.773~780 (2012), 한국원자력학회
- Boric Acid Corrosion of Light Water Reactor Pressure Vessel Materials, "J.-H. Park", ~, pp.NUREG (2005), CR-6875
- D. A. Jones, "Principles and Prevention of Corrosion", pp.31~ (1996), Prentice Hall