Irradiation of nuclear materials

This teaching unit covers the concepts needed to understand the consequences of irradiation on ceramic materials (fuels, specific containment matrices). In the case of nuclear fuel materials, this involves analyzing degradation phenomena within the materials (point defects, extended defects) and the associated consequences on long-term behavior under storage or disposal conditions. In this context, irradiation/leaching couplings will also be addressed.

Hourly volumes:

            CM: 12 p.m.

            Tutorial: 8 hours

The objective of this teaching unit is to address issues related to the behavior of ceramic materials under physical stress (irradiation). A description of the basic phenomena (particle-matter interaction) that cause defect formation processes in solids will be provided. This will be followed by a study of the consequences of irradiation on the evolution of the macroscopic properties of different ceramic-type materials (fuels, conditioning matrices, structural materials). The irradiation/dissolution coupling will also be studied.

Basic elements of radioactivity

Radiation protection / Radiation-matter interactions

Continuous assessment

Behavior of materials under irradiation

• Defects in materials
  • Particle/matter interaction - Electronic excitations / ballistic collisions - Creation of defects
  • Calculation of irradiation damage: DPA, numerical calculation methods (SRIM code), radiolytic yield
  • Spot defects / Extended defects – Analysis methods
• The different materials under irradiation
  • Influence of primary defects on the usage properties 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): Master's in Chemistry Secretariat

Master's degree in Chemistry @ umontpellier.fr