Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2017, Vol. 28 ›› Issue (8): 107 doi: 10.1007/s41365-017-0269-9

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Creep rupture assessment for Level-2 PSA of a 2-loop PWR: accounting for phenomenological uncertainties

Faramarz Yousefpour1, Seyed Mohsen Hoseyni2, Seyed Mojtaba Hoseyni2, Seyed Ali Hashemi Olia2, Kaveh Karimi2   

  1. 1 Nuclear Science and Technology Research Institute, Tehran, Iran 2 Young Researchers and Elite Club, East Tehran Branch, Islamic Azad University, Tehran, Iran
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Faramarz Yousefpour, Seyed Mohsen Hoseyni, Seyed Mojtaba Hoseyni, et al.. Creep rupture assessment for Level-2 PSA of a 2-loop PWR: accounting for phenomenological uncertainties.Nuclear Science and Techniques, 2017, 28(8): 107     doi: 10.1007/s41365-017-0269-9
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Abstract:

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 PSA 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. The probability for steam generator tube creep rupture is estimated at 0.17

Key words: IDPSA, Creep rupture, Severe accident, Station blackout, TISGTR, PSA Level-2