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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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.