Initiating Event Selection and Analysis for Probabilistic Safety Assessment of Korea Research Reactor 


Vol. 36,  No. 2, pp. 101-110, Apr.  2021
10.14346/JKOSOS.2021.36.2.101


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  Abstract

This paper presents the results of an initiating event analysis as part of a Level 1 probabilistic safety assessment (PSA) for at-power internal events for the Korea Research Reactor (KRR). The PSA methodology is widely used to quantitatively assess the safety of research reactors (RRs) in the domestic nuclear industry. Initiating event frequencies are required to conduct a PSA, and they considerably affect the PSA results. Because there is no domestic database for domestic trip events, the safety of RRs is usually assessed using foreign databases. In this paper, operating experience data from the KRR for trip events were collected and analyzed in order to determine the frequency of specific initiating events. These frequencies were calculated using two approaches according to the event characteristics and data availability: (1) based on KRR operating experience or (2) using generic data.

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  Cite this article

[IEEE Style]

이윤환, "Initiating Event Selection and Analysis for Probabilistic Safety Assessment of Korea Research Reactor," Journal of the Korean Society of Safety, vol. 36, no. 2, pp. 101-110, 2021. DOI: 10.14346/JKOSOS.2021.36.2.101.

[ACM Style]

이윤환. 2021. Initiating Event Selection and Analysis for Probabilistic Safety Assessment of Korea Research Reactor. Journal of the Korean Society of Safety, 36, 2, (2021), 101-110. DOI: 10.14346/JKOSOS.2021.36.2.101.

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