Containment materials

A general approach to containment materials will be developed during this course by addressing the desired properties of use, the different classes of containment matrices and the associated synthesis methods. The structure-properties relationships related to the containment of radionuclides and/or chemical toxic elements will also be described. The materials covered will be of the glass, glass-ceramic or ceramic type.

Hourly volumes* :

            CM : 12h

            TD : 8h

The objective of this teaching unit is to understand the approaches used to define, develop and characterize materials (glass, glass-ceramics, ceramics, hydraulic binders) intended for the containment of radionuclides and/or chemical toxic elements.

Basic elements in radioactivity

Solution chemistry applied to actinides

Advanced inorganic materials

Final test

• Properties of use sought and associated constraints:
• - Containment of radionuclides and chemical toxins (glass, glass-ceramics, ceramics, hydraulic binders)
• - Separation/sorting of radioelements by crystallization/precipitation operations
• Material classes and synthesis routes in nuclear environment:
• - Glasses (borosilicate, phosphate, aluminosilicate, ...)
• - Ceramic materials
• - Hydraulic binders
• Relationships between solid structures and expected properties (case studies) :
• - Formulations of glasses and ceramics in relation to waste flows (radioactive, toxic, etc.)
• - Hydraulic binder formulations for saline waste streams (sulfates, nitrates, etc.)

Administrative contact(s): Secretariat Master Chemistry

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