Reactor Stability Study

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 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.


  1. 1.
    Suda N (1969) Nuclear reactor kinetics and control. Dobunshoin, TokyoGoogle Scholar
  2. 2.
    Ash M (1965) Nuclear reactor kinetics. McGraw-Hill, New YorkGoogle Scholar
  3. 3.
    Yoshikawa T (2004) Classic control theory. Shokodo, TokyoGoogle Scholar
  4. 4.
    Enomoto, Tanabe et al (1985) The boiling water reactor: recent knowledge and forward perspective for stability. J. At. Energy Soc. Jpn 27(10):890–903Google Scholar
  5. 5.
    Anegawa, Ebata et al (1996) Recent topics relating to the BWR thermal-hydraulic stability. J. At. Energy Soc. Jpn 38(5):348–356Google Scholar
  6. 6.
    Takigawa Y et al (1987) Caorso limit cycle oscillation analysis with three-dimensional transient code TOSDYN-2. Nucl Technol 79:210–227Google Scholar
  7. 7.
    Nariai H et al (2001) Atomic Energy Society of Japan: “Present situation and issues for BWR thermal-hydraulic stability assessment”Google Scholar

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

Personalised recommendations