Irradiation of Nuclear Materials

This course covers the concepts necessary to understand the effects of irradiation on ceramic materials (fuels, specific containment matrices). In the case of nuclear fuel materials, the focus will be on analyzing degradation phenomena within the materials (localized defects, extended defects) as well as the associated effects on long-term behavior under storage or interim storage conditions. In this context, the interaction between irradiation and leaching will also be addressed.

Hourly volumes*:

            CM: 12:00 p.m.

            TD: 8:00 a.m.

The objective of this course is to address issues related to the behavior of ceramic materials under physical stress (irradiation). The fundamental phenomena (particle-matter interaction) that give rise to defect formation in solids will be described. This will be followed by a study of the effects of irradiation on changes in the macroscopic properties of various types of ceramic materials (fuels, packaging matrices, structural materials). The interaction between irradiation and dissolution will also be examined.

Basics of Radioactivity

Radiation Protection / Radiation-Matter Interactions

Ongoing Assessment

Behavior of Materials Under Radiation

• Defects in Materials
  • Particle-Matter Interaction - Electronic Excitation / Ballistic Collisions - Defect Formation
  • Calculation of radiation damage: DPA, numerical calculation methods (SRIM Code), radiolytic yield
  • Localized Defects / Extensive Defects – Analysis Methods
• Different Materials Under Radiation Exposure
  • Influence of Primary Defects on the Performance Properties and/or Structural Evolution of Materials
  • Case Studies: Fuels, Structural Materials, Special Containment Matrices, Transmutation Matrices

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

Administrative contact(s): Chemistry Master's Program Office

Master's in Chemistry @ umontpellier.fr