Multipoint Kinetics Modeling of Large Nuclear Reactors

  • S. Shimjith
  • A. Tiwari
  • B. Bandyopadhyay
Part of the Lecture Notes in Control and Information Sciences book series (LNCIS, volume 431)


The central problem in reactor analysis is the determination of the spatial flux and power distribution in the reactor core under steady state as well as transient operating conditions. There is, however, a considerable variation in the degree of accuracy and spatial details of the power distribution required in different facets of reactor analysis and design. Basically, the behavior of neutrons in a nuclear reactor is adequately described by the time-dependent Boltzmann transport equation [24, 38]. However, numerical solutions of the coupled time-dependent transport and delayed neutron precursors’ equations for reactor kinetics problems of practical interest are prohibitively difficult.


Reactor Core Nodal Model Large Nuclear Reactor Nodal Power Unstable Eigenvalue 
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Copyright information

© Springer-Verlag Berlin Heidelberg 2013

Authors and Affiliations

  1. 1.Indian Institute of Technology Bombay Scientific Officer (F)Bhabha Atomic Research CentreMumbaiIndia
  2. 2.Scientific Officer(H+) and ProfessorBhabha Atomic Research CentreMumbaiIndia
  3. 3.IDP in Systems and Control Engg.Indian Institute of Technology BombayMumbaiIndia

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