Natural circulation characteristics of an integral pressurized water reactor

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Abstract

Natural circulation potential is of great importance to the inherent safety of a nuclear reactor. This paper presents a theoretical investigation on the natural circulation characteristics of an integrated pressurized water reactor. Through numerically solved the one-dimensional model, the steady-state single phase conservative equations for the primary circuit and the steady-state two-phase drift-flux conservative equations for the secondary side of the once-through steam generator, the natural circulation characteristics are studied. Based on the preliminary calculation analysis, it is found that natural circulation mass flow rate is proportional to the exponential function of the power, and the value of the exponent is related to working conditions of the steam generator secondary side. The higher height difference between the core center and the steam generator center is favorable to the heat removal capacity of the natural circulation.

Original languageEnglish
Title of host publicationFourteenth International Conference on Nuclear Engineering 2006, ICONE 14
DOIs
StatePublished - 2006
EventFourteenth International Conference on Nuclear Engineering 2006, ICONE 14 - Miami, FL, United States
Duration: 17 Jul 200620 Jul 2006

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume2006

Conference

ConferenceFourteenth International Conference on Nuclear Engineering 2006, ICONE 14
Country/TerritoryUnited States
CityMiami, FL
Period17/07/0620/07/06

Keywords

  • Height difference
  • Natural circulation
  • Theoretical investigation

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