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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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State legislation: Delaware delving into nuclear energy possibilities
A bill that would create a nuclear energy task force in Delaware has passed the state Senate and is now being considered in the House of Representatives.
Scott Briggs (York Univ), Jennifer McKelvie (Canadian Inst for Advanced Research), Magdalena Krol (York Univ)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 317-321
The long-term storage of nuclear waste is an engineering challenge being investigated around the world. The Canadian deep geological repository (DGR) design consists of a multiple barrier system including a used fuel container (UFC) surrounded by bentonite within a low permeability host rock. The bentonite buffer that surrounds the UFC is designed to limit the ingress of chemical species towards the UFC and minimize egress of radionuclides away from the UFC. In addition, the UFC consists of an inner steel container that resists the expected pressures at 500-800 m below the ground surface and is coated in copper which acts as a barrier against corrosion. Sulphide that is remotely produced by sulphate reducing bacteria far away from the UFC, can diffuse through the bentonite buffer and result in UFC corrosion. Modelling the transport of sulphide is therefore critical to determining the expected corrosion on the surface of the UFC. Accordingly, a three dimensional (3D) finite element model of the Canadian DGR was developed with emphasis on capturing the unique 3D UFC geometry and expected repository layout. The numerical model was implemented using COMSOL Multiphysics, and sulphide diffusion through the buffer was simulated using Fick’s Law incorporating a temperature dependent diffusion coefficient. The temperature in the DGR is expected to peak close to 100°C in the first 100 years due to the thermal radiation of heat from the used nuclear fuel. The results show an interesting variation of sulphide transport throughout the DGR indicating the benefits of 3D modelling. In addition, diffusion coefficients increase by a factor of 4 compared to background levels with temperatures near 100°C and lead to a sulphide flux increase in the DGR. The model includes diffusion coefficients that change spatially and temporally to fully capture the effect on sulphide flux.