International audienceIn the current work, we analyze the thermal behavior and thermo-mechanical response of a high-level nuclear waste (HLW) package. Based on a thermal vitrification experiment with inactive borosilicate glass, we report a method to model, simulate and predict the HLW thermal behavior over time-scales corresponding to the useful lifespan of a HLW, e.g. potentially in hundreds of thousands of years. The proposed thermal approach relies on an inverse method using homogenized fluxes at the surfaces of the HLW package during the whole vitrification process. The resulting thermal modeling and simulation is then used as input in a viscoelastic structural analysis of the thermal stress build-up inside the glass block. This invers...
Vitrification is currently the most widely used technology for the treatment of high level radioacti...
Disposal of high-level radioactive wastes involves vitrification of a mixture of waste products and ...
International audienceVapor hydration of a simulated typical French nuclear intermediate-level waste...
International audienceIn the current work, we analyze the thermal behavior and thermo-mechanical res...
10 pagesInternational audienceFor a better understanding of the thermomechanical behavior of glasses...
International audienceThe modeling of the viscoelastic stress evolution and specific volume relaxati...
This paper presents the results of a Time-Temperature-Transformation (TTT) study of the effect of di...
Degree awarded: Ph.D. Physics. The Catholic University of AmericaThis dissertation can be viewed by ...
International audienceSeveral chemical reactions take place during the vitrification of high-level n...
This work forms part of a Collaborative Awards in Science and Engineering industrial studentship (iC...
We study the thermomechanical behavior of vitrified waste packages by multiphysics modeling. The pac...
Vitrification is currently the most widely used technology for the treatment of high level radioacti...
Disposal of high-level radioactive wastes involves vitrification of a mixture of waste products and ...
International audienceVapor hydration of a simulated typical French nuclear intermediate-level waste...
International audienceIn the current work, we analyze the thermal behavior and thermo-mechanical res...
10 pagesInternational audienceFor a better understanding of the thermomechanical behavior of glasses...
International audienceThe modeling of the viscoelastic stress evolution and specific volume relaxati...
This paper presents the results of a Time-Temperature-Transformation (TTT) study of the effect of di...
Degree awarded: Ph.D. Physics. The Catholic University of AmericaThis dissertation can be viewed by ...
International audienceSeveral chemical reactions take place during the vitrification of high-level n...
This work forms part of a Collaborative Awards in Science and Engineering industrial studentship (iC...
We study the thermomechanical behavior of vitrified waste packages by multiphysics modeling. The pac...
Vitrification is currently the most widely used technology for the treatment of high level radioacti...
Disposal of high-level radioactive wastes involves vitrification of a mixture of waste products and ...
International audienceVapor hydration of a simulated typical French nuclear intermediate-level waste...