Diffusion of neutrons in nuclear reactors : an introductory textbook for neutronics /

Bibliographic Details
Main Author:	Grard, Hubert (Author)
Corporate Author:	EBSCOhost
Format:	eBook
Language:	English
Published:	Cham : Springer, 2026.
Series:	Physics and Astronomy Series.
Subjects:	Neutron transport theory. Nuclear reactors. Théorie du transport des neutrons. Réacteurs nucléaires. nuclear reactors. Electronic books.
Online Access:	Connect to the full text of this electronic book

Table of Contents:

1.A few calculations with monokinetic neutrons.-2.Neutron density, ﬂux and current
3.Fission spectrum and thermal spectrum
4.Slowing down and thermalization
5.Resonant absorption. Doppler feedback eﬀect
6.Diﬀusion current and ﬂux gradient. Fick’s law applied to neutronics
7.Equations expressing the conservation of neutrons
8.Source neutrons in a scattering and absorbing medium
9.The theory of age
10.The theory of diﬀusion applied to ﬁssile systems with monoki-netic neutrons
11.Boundary conditions
12.Two Groups diﬀusion
13.The critical reactor with two neutron groups
14.From diﬀusion theory to point kinetics
15.Subcritical reactor
16.Highlighting of harmonics
17.Eﬀects of control rods
18.Poisoning of the reactors
19.Dynamic Rod Weight Measurement
20.Adjoint ﬂux and perturbation method.