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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
R. A. Borrelli, Olivier Thivent, Joonhong Ahn
Nuclear Technology | Volume 174 | Number 1 | April 2011 | Pages 94-108
Technical Paper | Geochemistry and Ground Transport of RW | doi.org/10.13182/NT11-A11683
Articles are hosted by Taylor and Francis Online.
The study presented in this paper examines the potential of extruded bentonite as an additional barrier to radionuclide release to the far field. In the saturated repository, the bulk bentonite buffer surrounding the waste package will extrude into an intersecting fracture. Subsequent radionuclide release and transport into the fracture could be affected by the presence of this extrusion region. A model was previously established to describe the transport of radionuclides in the fracture that also includes this extruded bentonite. In this paper, we study model simulations for an idealized case of cesium transport through the extrusion region at elevated temperature. Extrusion speed will increase and cesium transport is enhanced with temperature; however, this extrusion region shows favorable performance in confining cesium at all temperatures. This study suggests that additional, rigorous modeling of this extrusion region as a barrier to radionuclide release with consideration of performance assessment studies is warranted.