Reactor Stability Study

  • Katsuo Suzuki
  • Hiroshi Ono
  • Shuhei Miyake
Part of the An Advanced Course in Nuclear Engineering book series (ACNE)


Usually, the one-point core dynamic approximation model can be expressed by the following equation system


Void Fraction Pressure Loss Fuel Assembly Core Stability Channel Stability 
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Copyright information

© Springer Japan 2013

Authors and Affiliations

  1. 1.Japan Nuclear Energy Safety OrganizationTokyoJapan
  2. 2.Toshiba CorporationTokyoJapan
  3. 3.Mitsubishi Heavy Industries, Ltd.TokyoJapan

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