Arkansas Nuclear One Unit One risk-analysis results
G.J. Kolb, D.M. Kunsman
Abstract
G.J. Kolb, D.M. Kunsman
Abstract
This paper presents the results of the analysis of Arkansas Nuclear One Unit One nuclear power plant which was performed as part of the Interim Reliability Evaluation Program (IREP). ANO-1 is a Babcock and Wilcox pressurized water reactor. The IREP has several objectives, three of which are achieved by the analysis presented in this paper. The three objectives met are: (1) the identification of those accident sequences which are expected to dominate the public health and safety risks associated with operation of ANO-1, (2) the development of state-of-the-art plant system models which can be used as a foundation for subsequent, more intensive applications of probabilistic risk assessment on ANO-1, and (3) the increase in number of experienced practitioners of probabilistic risk assessment. The estimated core melt frequency for ANO-1 is similar to values predicted by probabilistic risk assessments of other light water reactors.
A significance statement is not available in the OpenAlex record.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
This paper presents the results of the analysis of Arkansas Nuclear One Unit One nuclear power plant which was performed as part of the Interim Reliability Evaluation Program (IREP). ANO-1 is a Babcock and Wilcox pressurized water reactor. The IREP has several objectives, three of which are achieved by the analysis presented in this paper. The three objectives met are: (1) the identification of those accident sequences which are expected to dominate the public health and safety risks associated with operation of ANO-1, (2) the development of state-of-the-art plant system models which can be used as a foundation for subsequent, more intensive applications of probabilistic risk assessment on ANO-1, and (3) the increase in number of experienced practitioners of probabilistic risk assessment. The estimated core melt frequency for ANO-1 is similar to values predicted by probabilistic risk assessments of other light water reactors.
Key concepts: Probabilistic risk assessment, Probabilistic logic, Nuclear power plant, Risk assessment, Nuclear power, Unit (ring theory), Interim, Reliability (semiconductor)