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Incorporation of Corrosion Mechanisms into a State-dependent Probabilistic Risk Assessment

Lewandowski, Radoslaw
http://rave.ohiolink.edu/etdc/view?acc_num=osu1366171631

Abstract Details

2013, Master of Science, Ohio State University, Nuclear Engineering.
The need for extending lifetimes of nuclear power plants and an increased interest in passive safety systems in Generation III+ and small modular reactors has brought a new focus in probabilistic risk assessment (PRA) to the treatment of passive systems, structures and components (SSCs). Although previously thought to play a lesser role in determining plant risk, research and industry experience have shown that degradation mechanisms of passive SSCs increase in importance with extended operating lifetimes. The case study analyzed in this research involves an accident scenario, in which steam generator tubes degraded by stress corrosion cracking rupture due to depressurization following a steam line break resulting from flow-accelerated corrosion. This study was performed by developing a state-dependent risk model. The model has the capability of using traditional PRA tools such as event trees and fault trees to determine a state-dependent core damage frequency. Unlike traditional PRA, which emphasizes active components, this methodology was used with a mechanistic aging model of a passive component. In addition, the model considers the effectiveness of the surveillance program and may be further developed to account for the possibility of component rejuvenation. Thus, the model allows for a time-dependent assessment of plant aging on risk. The application of the model to the Zion Nuclear Power Station has indicated that the maximum core damage frequency over the plant lifetime for a steam line break-induced tube rupture would occur in the 20th year of plant operation. The model also predicts the time progression of tube plugging and the frequency of spontaneous steam generator tube ruptures. Based on historical data, the rates of degradation calculated in the analysis appear to be reasonable, but somewhat conservative.
Tunc Aldemir (Committee Member)
Richard Denning (Committee Member)
Jinsuo Zhang (Advisor)
109 p.
Nuclear Engineering
Probabilistic Risk Assessment; Stress Corrosion Cracking; Flow-accelerated Corrosion; Passive Components

Recommended Citations

Citations

  • Lewandowski, R. (2013). Incorporation of Corrosion Mechanisms into a State-dependent Probabilistic Risk Assessment [Master's thesis, Ohio State University]. OhioLINK Electronic Theses and Dissertations Center. http://rave.ohiolink.edu/etdc/view?acc_num=osu1366171631

    APA Style (7th edition)

  • Lewandowski, Radoslaw. Incorporation of Corrosion Mechanisms into a State-dependent Probabilistic Risk Assessment. 2013. Ohio State University, Master's thesis. OhioLINK Electronic Theses and Dissertations Center, http://rave.ohiolink.edu/etdc/view?acc_num=osu1366171631.

    MLA Style (8th edition)

  • Lewandowski, Radoslaw. "Incorporation of Corrosion Mechanisms into a State-dependent Probabilistic Risk Assessment." Master's thesis, Ohio State University, 2013. http://rave.ohiolink.edu/etdc/view?acc_num=osu1366171631

    Chicago Manual of Style (17th edition)

osu1366171631
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© 2013, all rights reserved.
This open access ETD is published by The Ohio State University and OhioLINK.