A Study on the Final Probabilistic Safety Assessment for the Jordan Research and Training Reactor 


Vol. 35,  No. 3, pp. 86-95, Jun.  2020
10.14346/JKOSOS.2020.35.3.86


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  Abstract

This paper describes the work and the results of the final Probabilistic Safety Assessment (PSA) for the Jordan Research and Training Reactor (JRTR). This final PSA was undertaken to assess the level of safety for the design of a research reactor and to evaluate whether it is probabilistically safe to operate and reliable to use. The scope of the PSA described here is a Level 1 PSA, which addresses the risks associated with core damage. After reviewing the documents and its conceptual design, nine typical initiating events were selected regarding internal events during the normal operation of the reactor. AIMS-PSA (Version 1.2c) was used for the accident quantification, and FTREX was used as the quantification engine. 1.0E-15/yr of the cutoff value was used to deliminate the non-effective Minimal Cut Sets (MCSs) when quantifying the JRTR PSA model. As a result, the final result indicates a point estimate of 2.02E-07/yr for the overall Core Damage Frequency (CDF) attributable to internal initiating events in the core damage state for the JRTR. A Loss of Primary Cooling System Flow (LOPCS) is the dominant contributor to the total CDF by a single initiating event (9.96E-08/yr), and provides 49.4% of the CDF. General Transients (GTRNs) are the second largest contributor, and provide 32.9% (6.65E-08/yr) of the CDF

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  Cite this article

[IEEE Style]

이윤환, "A Study on the Final Probabilistic Safety Assessment for the Jordan Research and Training Reactor," Journal of the Korean Society of Safety, vol. 35, no. 3, pp. 86-95, 2020. DOI: 10.14346/JKOSOS.2020.35.3.86.

[ACM Style]

이윤환. 2020. A Study on the Final Probabilistic Safety Assessment for the Jordan Research and Training Reactor. Journal of the Korean Society of Safety, 35, 3, (2020), 86-95. DOI: 10.14346/JKOSOS.2020.35.3.86.

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