Abstract

Vitrification of high-level nuclear waste worldwide: Historical perspective, current status and future challenges

Vitrification of high-level nuclear waste worldwide: Historical perspective, current status and future challenges

Ashutosh Goel 1, Paul A. Bingham 2, John McCloy 3, Kai Xu 4, Sophie Schuller 5 John Vienna 6 Albert Kruger 7

1 Department of Material Science and Engineering, Rutgers, The State University of New Jersey, Piscataway, NJ 08854, United States
2 Materials and Engineering Research Institute, Sheffield Hallam University, City Campus, Sheffield, S1 1WB South Yorkshire, UK
3 School of Mechanical and Materials Engineering, Washington State University, Pullman, Washington, USA
4 State Key Laboratory of Silicate Materials for Architectures, Wuhan University of Technology, Wuhan 430070, P.R. China
5 CEA, DES, ISEC, Université Montpellier, Marcoule, France
6 Pacific Northwest National Laboratory, Richland, WA 99354, USA
7 U.S. Department of Energy, Office of River Protection, Richland, WA 99354, USA

The idea of glass being a suitable matrix for the immobilization of nuclear waste was proposed in 1950s. Since then, vitreous waste forms have been the most widely accepted candidates for the immobilization of high-level nuclear waste (HLW) worldwide. While several countries are in the process of vitrifying their HLW, the others are still in the planning phase or starting in the near future. Although the general matrix of HLW glasses remains the same, i.e., borosilicate, the overall design of glass compositions is different worldwide primarily due to the different waste chemistries, thus resulting in different scientific and engineering challenges. The lecture will present a historical perspective of the high-level waste vitrification followed by its current status and future challenges at a global level.