Irradiation of nuclear materials

This teaching unit deals with the notions necessary to understand the consequences of an irradiation on ceramic materials (fuels, specific containment matrices). In the case of nuclear fuel materials, it will analyze the degradation phenomena within the materials (point defects, extensive defects) as well as the associated consequences on the long-term behavior in storage conditions. In this context, the irradiation/leaching couplings will also be addressed.

Hourly volumes* :

            CM : 12h

            TD : 8h

The objective of this teaching unit is to address the problems related to the behavior of ceramic materials under physical stress (irradiation). A description of the elementary phenomena (particle-matter interaction) at the origin of the defect creation processes in the solid will be described. The consequences of irradiation on the evolution of macroscopic properties of various ceramic materials (fuels, conditioning matrices, structural materials) will be studied. The irradiation/dissolution coupling will also be studied.

Basic elements in radioactivity

Radiation protection / Radiation-matter interactions

Continuous control

Behavior of materials under irradiation

• Defects in materials
  • Particle/matter interaction - Electronic excitations / ballistic collisions - Defect creation
  • Calculation of the irradiation damage: the DPA, numerical methods of calculation (SRIM code), radiolytic yield
  • Point defects / Extended defects - Analysis methods
• The different materials under irradiation
  • Influence of primary defects on the properties of use and/or structural evolution of materials
  • Case studies: Fuels, structural materials, specific containment matrices, transmutation matrices

Lectures and tutorials will be supplemented by case studies and bibliographic tutorials.

Administrative contact(s): Secretariat Master Chemistry

master-chimie @ umontpellier.fr (master-chimie @ umontpellier.fr)