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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2013.1
- 수록면
- 85 - 92 (8page)
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초록· 키워드
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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.
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참고문헌 (11)
참고문헌 신청
A. Roth / 2005 / / Proceedings of the 12th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor : 795 ~
A. Roth / 2007 / / Proceedings of the 13th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor 29
D. A. Jones / 1996 / Principles and Prevention of Corrosion / Prentice Hall : 31 ~
H. Xu / 2005 / / Proceedings of the 12th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor : 855 ~
J. H. Park / 2005 / / Proceedings of the 12th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor : 459 ~
A. Roth / 2007 / / Proceedings of the 13th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor 29
D. A. Jones / 1996 / Principles and Prevention of Corrosion / Prentice Hall : 31 ~
H. Xu / 2005 / / Proceedings of the 12th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor : 855 ~
J. H. Park / 2005 / / Proceedings of the 12th Int’l Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor : 459 ~
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