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Simulation of Natural Circulation Test of The Bushehr's VVER-1000 Nuclear Power Plant with RELAP5

Vafa Toroghi, Mojtaba | 2017

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 50310 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Ghofrani, Mohammad Bagher
  7. Abstract:
  8. Safety is an important factor in the nuclear power plants due to its inherent human and environmental hazards. Therefore, in order to ensure the safety of the plant and proper functioning of its various components, a series of commissioning tests should be conducted according to international nuclear power plants standards, before its operational exploitation. On the other hand, safety of the plant can be guaranteed by modeling transient states and possible scenarios of accidents in different situations. In this study, a commissioning test of Bushehr Nuclear Power Plant (BNPP) and its associated accident is modelled by gathering geometric data and information about the facilities installed in the plant using the RELAP5 code and the SNAP graphical interface. At first, the obtained simulation results of the steady state at nominal power are compared with the safety documents of power plant between which a good agreement was observed. Afterwards, the natural circulation test of the coolant fluid of BNPP is modeled using RELAP5 code and its results are compared with experimental outcomes, concluding good agreement. By this, the developed model for transient analysis obtained by RELAP5 code has been validated with experimental results. Analysis indicates that the intended test objectives were successfully implemented.Some of these objectives include: Estimation of the natural circulation of the coolant fluid for removal of the decay heat without the presence of pumps, joint operations of main and auxiliary systems when the plan transfers to a new power level, and the functioning of safety system without operator intervention.Finally, the loss of off-site power accident is modeled based on available scenario in the Final Safety Analysis Report (FSAR) of BNPP using RELAP5 code and the obtained data are compared with FSAR results, showing good agreement. Accident analysis results indicates that operation of safety systems control the accident, pressures of the primary and secondary circuits do not exceed permitted limits and finally, the safety barriers of plant are intact
  9. Keywords:
  10. Loss of Offsite Power (LOOP)Accident ; RELAP5 Code ; Experimental Results ; Bushehr Nuclear Power Plant ; Natural Circulation Boiling ; Symbolic Nuclear Analysis Package (SNAP) Graphical Interface

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