The major advantage of PSA is the possibility of in-depth qualitative and quantitative analysis of NPP actual configuration with definition of factors introducing a significant contribution to the general risk of reactor core damage. However main lack of the PSA current models is neglect of equipment ageing effects. Neglecting of ageing effects in PSA could lead to incorrectness of risk profile and influent on risk-informed decision making process. To solve this issue incorporation of ageing aspects into PSA models for Armenian NPP Unit 2 was initiated. Implementation of ageing trend analysis for all PSA components is insuperable effort, so the first step of the analysis is component selection activity. This paper is addressing the approach on component selection for ageing-trend analysis within PSA models. Presented approach is based on ageing effect and risk importance data. The procedure was developed and implemented in the framework of ageing aspects incorporation into PSA level 1 model for Armenian NPP Unit 2.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Approach on Component Selection for Ageing-Trend Analysis Within PSA Models
Shahen Poghosyan,
Shahen Poghosyan
Nuclear and Radiation Safety Centre, Yerevan, Armenia
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Armen Amirjanyan,
Armen Amirjanyan
Nuclear and Radiation Safety Centre, Yerevan, Armenia
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Albert Malkhasyan
Albert Malkhasyan
Nuclear and Radiation Safety Centre, Yerevan, Armenia
Search for other works by this author on:
Shahen Poghosyan
Nuclear and Radiation Safety Centre, Yerevan, Armenia
Armen Amirjanyan
Nuclear and Radiation Safety Centre, Yerevan, Armenia
Albert Malkhasyan
Nuclear and Radiation Safety Centre, Yerevan, Armenia
Paper No:
ICONE17-75029, pp. 307-311; 5 pages
Published Online:
February 25, 2010
Citation
Poghosyan, S, Amirjanyan, A, & Malkhasyan, A. "Approach on Component Selection for Ageing-Trend Analysis Within PSA Models." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 307-311. ASME. https://doi.org/10.1115/ICONE17-75029
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