Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Self-pressurization analysis of the natural circulation integral nuclear reactor using a new dynamic model

  • Pilehvar, Ali Farsoon (Department of Nuclear Engineering, Faculty of Advanced Sciences & Technologies, University of Isfahan) ;
  • Esteki, Mohammad Hossein (Department of Biomedical Engineering, Faculty of Engineering & Technologies, University of Isfahan) ;
  • Hedayat, Afshin (Reactor and Nuclear Safety School, Nuclear Science and Technology Research Institute (NSTRI)) ;
  • Ansarifar, Gholam Reza (Department of Nuclear Engineering, Faculty of Advanced Sciences & Technologies, University of Isfahan)
  • Received : 2017.09.13
  • Accepted : 2018.03.13
  • Published : 2018.06.25
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Abstract

Self-pressurization analysis of the natural circulation integral nuclear reactor through a new dynamic model is studied. Unlike conventional pressurized water reactors, this reactor type controls the system pressure using saturated coolant water in the steam dome at the top of the pressure vessel. Self-pressurization model is developed based on conservation of mass, volume, and energy by predicting the condensation that occurs in the steam dome and the flashing inside the chimney using the partial differential equation. A simple but functional model is adopted for the steam generator. The obtained results indicate that the variable measurement is consistent with design data and that this new model is able to predict the dynamics of the reactor in different situations. It is revealed that flashing and condensation power are in direct relation with the stability of the system pressure, without which pressure convergence cannot be established.

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