Study level
BAC +5
ECTS
2 credits
Component
Faculty of Science
Description
This course covers the concepts needed to understand the consequences of irradiation on ceramic materials (fuels, specific containment matrices). In the case of nuclear fuel materials, the aim is to analyze degradation phenomena within materials (point defects, extensive defects) and the associated consequences for long-term behavior under storage or disposal conditions. In this context, irradiation/leaching couplings will also be addressed.
Hourly volumes* :
CM: 12h
TD : 8h
Objectives
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 processes of creation of defects in the solid will be described. The study of the consequences of irradiation on the evolution of the macroscopic properties of different ceramic-type materials (fuels, conditioning matrices, structural materials) will follow. The irradiation/dissolution coupling will also be studied.
Necessary prerequisites
Basics of radioactivity
Radioprotection / Radiation-matter interactions
Knowledge control
Continuous control
Syllabus
Behavior of materials under irradiation
- Defects in materials
- Particle/matter interaction - Electronic excitations / ballistic collisions - Creation of defects
- Calculation of radiation damage: DPA, numerical calculation methods (SRIM Code), radiolytic yield
- Point defects / Extended defects – Analysis methods
- Different materials under irradiation
- Influence of primary defects on the usage properties and/or structural evolution of materials
- Case studies: Fuels, structural materials, specific confinement matrices, transmutation matrices
The lectures and tutorials will be supplemented by case studies and bibliographic tutorials.
Further information
Administrative contact(s): Master of Chemistry secretariat