Published 1998 | Version v1
Book

Neutron-nucleus interactions and fission. Chapter 1

Creators

Description

The central problem in nuclear-reactor kinetics is to predict the evolution in time of the neutron population in a multiplying medium. Point kinetics allows study of the global behaviour of the neutron population from the average properties of the medium. Before tackling, in the following chapters, the equations governing the time variation of the reactor power (proportional to the total neutron population), the properties of a neutron-multiplying medium shall be discussed briefly. After recalling a number of definitions, a qualitative description shall be given of the principal nuclear reactions at play in a self-sustaining chain reaction, with emphasis on the source of fission neutrons. Since delayed neutrons play a crucial role in reactor kinetics, their production in a reactor shall be described in greater detail. (author)

Part of:
Introduction to nuclear reactor kinetics

Additional details

Publishing Information

Publisher
Polytechnic International Press, Editions de l'Ecole Polytechnique de Montreal
Imprint Place
Montreal, Quebec (Canada)
ISBN
2-553-00700-0
Imprint Title
Introduction to nuclear reactor kinetics
Imprint Pagination
351 p.
Journal Page Range
p. 1-24

Optional Information

Notes
10 tabs., 11 figs. Imprint:113 refs. Translation of 'Introduction a la cinetique des reacteurs nucleaires', Montreal, Quebec (CA), 1992