Scope and objectives
Cementation is a widely applied technique for the conditioning of low – and intermediate – level radioactive wastes. However, specific issues have still to be addressed, such as the limitation of adverse cement-waste interactions which may affect the quality of the resulting solidified waste form, or the understanding and prediction of long-term properties of the waste packages and cement barriers. There is also a need for safe processes minimizing the production of secondary wastes, and for monitoring techniques of cemented waste packages and cement barriers. The objective is to promote the exchange of advanced information on the ongoing research and development activities dealing with cementation of nuclear wastes, from elaboration of waste packages to their final disposal.
The symposium
A 3 day conference talks and posters, will be held in Avignon, France, from May 4 to 6, 2022, at the Palais des Papes, an historical place in the center of the town.
Topics
– Performance requirements and implementation methods
– Formulation for various kinds of wastes (metallic wastes, ashes, spent sorbents including ion exchange resins and zeolites, coprecipitation sludges, evaporator concentrates and other saline solutions, organic-containing wastes)
– Formulation methodologies
– Processes involved: mixing device designs, packaging options ; engineering feasibility and implementation in real site
– Cement-waste interactions
– Factors influencing rheology, setting, hardening, hydration rate, heat production, pH and pore solution evolution
– Evolution of mineralogy and microstructure
– Low pH cements
– Calcium aluminate and sulfoaluminate cements
– Geopolymers
– Phosphate cements (magnesium, calcium…)
– NEW! Interactions between new binders and conventional construction materials
– Waste / cement / aggregate interactions
– Differed ettringite formation
– Effect of bg and a irradiation: radiolytic gas production, stability of cement hydrates and admixtures
– Corrosion of metallic waste
– Gas evacuation
– Micro and macro-cracking
– NEW! Chemo-mechanical modelling
– Leaching by aggressive solutions (chloride, sulfate…), carbonation
– Effect of temperature
– Redox state evolution
– Radionuclides retention
– Liquid, gas, and contaminant transport under unsaturated or saturated conditions
– Interactions with other cement barriers
– Modelling of long-term behavior – saturated versus unsaturated transport
NEW!
– Monitoring techniques, remote monitoring, potential of robotics for monitoring condition of waste packages and waste forms
– Methods for detecting and quantifying concrete contamination
– Methodology for service life extrapolation
– Methods for reworking non-compliant cement waste forms
About Sfen
The French Nuclear Society is the French knowledge hub for nuclear energy. Created in 1973, the Sfen provides a space where all those who are interested in nuclear energy and its applications can obtain and exchange information.