Faramarz Yousefpour, Seyed Mohsen Hoseyni, SeyedMojtaba Hoseyni, et al. Creep rupture assessment for Level-2 PSA of a 2-loop PWR: Accounting for phenomenological uncertainties. [J]. Nuclear Science and Techniques 28(8):107(2017)
Faramarz Yousefpour, Seyed Mohsen Hoseyni, SeyedMojtaba Hoseyni, et al. Creep rupture assessment for Level-2 PSA of a 2-loop PWR: Accounting for phenomenological uncertainties. [J]. Nuclear Science and Techniques 28(8):107(2017) DOI： 10.1007/s41365-017-0269-9.
Creep rupture assessment for Level-2 PSA of a 2-loop PWR: Accounting for phenomenological uncertainties
The Level-2 Probabilistic Safety Assessment (PSA) of pressurized water reactors studies the possibility of creep rupture for major reactor coolant system components during the course of high pressure severe accident sequences. The present paper covers this technical issue and tries to quantify its associated phenomenological uncertainties for the development of Level-2 PSA. A framework is proposed for the formal quantification of uncertainties in the Level-2 PSA model of a PWR type nuclear power plant using an integrated deterministic and probabilistic safety assessment approach. This is demonstrated for estimation of creep rupture failure probability in station blackout severe accident of a 2-loop PWR, which is the representative case for high pressure sequences. MELCOR 1.8.6 code is employed here as the deterministic tool for the assessment of physical phenomena in the course of accident. In addition, a MATLAB code is developed for quantification of the probabilistic part by treating the uncertainties through separation of aleatory and epistemic sources of uncertainty. Theprobability for steam generator tube creep rupture is estimated at 0.17.
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