Introduction to nuclear engineering - Tome 1 - Neutronics and materials

Despite its division into four disciplines (Volume 1 and 2), the present book should in no way be confused with specialized treatises on each of these disciplines. Each part is limited to what is necessary: to understand the general problems posed by the nuclear industry for students of atomic engineering who wish to draw up an overall reactor project. Within the limited framework of the above objective, the calculation methods indicated and/or the criteria for selecting different engineering solutions can be used to draw up a preliminary design for a reactor, without the need for specialist knowledge or the use of computers. Content: 1 - Neutronics: Reminders of nuclear physics; Exercise in calculating cross sections; Chain reactions and neutron combustion; Neutron flux; Exercise on calculating the average flux in a reactor; Neutron scattering; Criticality of a multiplicative medium; Exercise in calculating critical dimensions; Spatial flux distribution in a heterogeneous thermal reactor; Spectral distribution of neutron flux at a given point; Reactor kinetics in the vicinity of criticality; Reactivity variations during operation; Neutronic control of the reactor; 2 - Materials and the fuel cycle: Metallurgy basics (Crystalline structures; Polycrystalline aggregates and crystalline phases; Plastic deformation and fracture; Fatigue and creep; Action of radiation); Nuclear materials (General information on materials; Uranium (and enrichment); Plutonium (reprocessing and waste); Thorium; Heavy water; Graphite; Beryllium; Steels; Zirconium; Control absorbents); Containment and protection (Fuel element; Pressure vessels; Protection)