Neutronic Analysis For Nuclear Reactor Systems pp 401-426 | Cite as

# Reactor Kinetics and Point Kinetics

## Abstract

The point kinetics model can be obtained directly from the space- and time-dependent transport equations. However, these equations are too complicated to be of any practical application. The diffusion approximation, obtained by keeping only the PI terms of the spherical harmonic expansion in the angular variable of the directional flux, is frequently used in neutronic analysis. This chapter discusses reactor characteristics that change because of changing reactivity. A basic approach using a minimum of mathematics has been followed. Emphasis has been placed on distinguishing between prompt and delayed neutrons and showing relationships among reactor variables, *k*_{eff}, period, neutron density, and power level.

## References

- 1.J. Koclas,
*Neutronic Analysis of Reactor*, Nuclear Engineering Department at Ecole Polytechnique de Montreal, February 1998Google Scholar - 2.J. Duderstadt, L. Hamilton,
*Nuclear Reactor Analysis*(John Wiley Publishing Company, 1976)Google Scholar