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Probability Safety Assessment of Steam Generator Tube Rupture In Bushehr Nuclear Power Plant With SAPHIRE Code

Jamshidi, Mohammad Javad | 2014

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 45541 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Ghofrani, Mohammad Bagher
  7. Abstract:
  8. In the absence of appropriate control, several accidents in the nuclear power, lead to serious consequences including core melted and radiation leakage outside reactor containment. In all these events, when core melted, the reactor operation is always finished and all efforts are then directed to environmental impacts of radioactive materials to the external environment. However, the occurrence of events that would bypass reactor containment, have special significance, because all possible efforts in order to limit the leakage of radioactive materials to the external environment are ineffective. In this respect the occurrence of such incidents, as most of which is considered the worst nuclear accidents in addition to implementing strategies to reduce the frequency of occurrence of such incidents, the method of its management, being optimized so in minimum from more leaks of radioactive material to the external environment is prevented.in Bushehr nuclear power plant steam generator tube rupture, With an annual occurrence frequency of 1.37E-03 / y, ranked 13th in the 16-group event is initiated. In this project, analysis of steam generator tube rupture and its effect on core melt Frequency using SAPHIRE software has been examined and the results validate with Bushehr nuclear power plant.
    First, the entire event regardless of the common cause failures (CCF) model and the frequency of core melting 2.375E-007 was obtained. Then with adding common cause failures, the frequency of core-melting 5.052E-007 was obtained. The core melt frequency with Risk-Spectrum is (5.062E-007).
  9. Keywords:
  10. Probabilistic Safety Assesment (PSA) ; Initiating Events Analysis ; Common Cause Failure ; Failur of Steam Generator Tubes Small ; Heart Melt Frequency

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