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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Jean-Michel Bosgiraud, Christophe Baroux, Frédéric Bumbieler, Didier Crusset (Andra)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 52-61
Andra, the French national radioactive waste management agency, is in charge of studying the disposal of high-level and long-lived intermediate-level waste (HLW and ILW-LL) in a deep geological repository (aka Cigéo). After a brief description of HLW disposal package models, their main functions are presented (handling purposes, containment of radioactive substances, criticality hazard control, delaying water contact with vitrified matrix, etc.). The horizontal steel cased disposal cell (0.7m ID micro-tunnel) inside which the disposal packages will be stored is also presented. The design options and the manufacturing processes of the disposal package are then described in order to show how the best technologies have been selected to ensure that the leak and gas tightness of the overpack is maintained as long as possible (and at least 500 years).
The following part of the paper is then focused on a description of the numerical simulations and corrosion tests (general corrosion, pitting and crevice corrosion, stress corrosion cracking with influence of the evolution of the water chemistry, temperature and radiolysis) performed in order to evaluate the mechanical behavior and durability of the disposal package. The mechanical studies focus on the behavior of a confined API5LX65MS steel casing (the disposal cell liner) submitted to general corrosion which governs the long term mechanical loading of the overpack. First numerical simulations performed to determine the ductile damage of a low alloy steel overpack subjected to both, general corrosion and localized mechanical loads are also presented.
