Experience with piping in German NPPs with respect to ageing-related aspects

Michel, Frank I.; Reck, H.; Schulz, Helmut

doi:10.1016/s0029-5493(01)00339-9

Cited by 28 publications

(3 citation statements)

References 2 publications

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“…To adequate protect carbon steels and copper alloys, the recommended pH range is 8.5-9.5 [42], some literature suggested to be below 9.3 [8]. Since German utilities replaced the copper-contained turbine with SS or titanium turbine and improved the pH to above 9.8, no damage with safety relevance occurred in German nuclear power plants due to FAC [43].…”

Section:  Ph Effectmentioning

confidence: 99%

Corrosion and deposition on the secondary circuit of steam generators

Xie

Zhang

2016

Journal of Nuclear Science and Technology

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This study conducts a critical review on the studies of material corrosion and deposition on the secondary circuit of a pressurized water reactor, especially on the steam generators (SGs). Available knowledge has shown that the structural materials in the environment of the secondary circuit are susceptible to flow-accelerated corrosion and deposition-induced degradation. The deposition of the non-volatile impurities, especially the corrosion products, on the SG surfaces can be a primary cause of material degradations, including stress corrosion cracking. The review will analyze the fouling mechanisms and behaviors, the source of impurities, corrosion mechanisms, and the factors that affect the deposition and corrosion behaviors.

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Section:  Ph Effectmentioning

confidence: 99%

Corrosion and deposition on the secondary circuit of steam generators

Xie

Zhang

2016

Journal of Nuclear Science and Technology

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“…One of the degradation mechanisms is local wall thinning in carbon steel pipes due to flow-accelerated corrosion (FAC) (Chexal et al, 1998;Michel et al, 2001). This occurs on the inside wall of the piping components, and the shape and growth of the thinning defect are mainly governed by the flow patterns in the piping system.…”

Section: Introductionmentioning

confidence: 99%

Experimental investigation of the failure behavior of notched wall-thinned pipes

Kim

Park

2006

Nuclear Engineering and Design

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“…탄소강 배관계통의 주요 손상기구로 알려져 있 다. (1,2) 따라서 탄소강 배관에서 감육결함은 원전의 , 안전성과 경제성 측면에서 중요한 관리 대상으로 고려되고 있다. (3) 원전 배관계통에서 감육결함 관리 의 핵심은 신뢰성 있는 두께 검사를 통한 결함의 검출이며, (1,4,5) 이를 위해 초음파 두께 측정 방법이 널리 사용되고 있다.…”

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