Published 1995
| Version v1
Book
Mathematical methods in neutronics
Creators
Description
This book presents the mathematical theory of nuclear reactors. It applies to engineers in neutronics and applied mathematicians. After a recall of the elementary notions of neutronics and of diffusion-type partial derivative equations, the theory of reactors criticality calculation is described. (J.S.)
Additional details
Additional titles
- Original title (French)
- Methodes mathematiques en neutronique
Publishing Information
- Publisher
- Editions EDF
- Imprint Place
- Paris (France)
- ISBN
- 2-212-01643-3
- Imprint Pagination
- 452 p.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 30043356
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CRITICALITY; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; NEUTRONS; REACTOR KINETICS EQUATIONS; REACTOR PHYSICS; REACTOR SAFETY
- Descriptors DEC
- BARYONS; ELEMENTARY PARTICLES; EQUATIONS; FERMIONS; HADRONS; NUCLEONS; SAFETY; TRANSPORT THEORY