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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Alyse Scurlock, Jocelyn Petty, Scott Woodbury, William Murphy (Duke Energy), Jay Wellwood (NAC International), Brady Hanson (PNNL), John Scaglione (ORNL)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 914-916
As part of the development of technical bases which support the extended storage and transportation of used nuclear fuel, Pacific Northwest National Laboratory (PNNL) has implemented detailed thermal analysis methods for the calculation of best estimate temperatures of Dry Cask Storage (DCS) systems. These methods were used to model a NAC International MAGNASTOR® cask located at the Catawba Nuclear Station (Catawba) which is operated by Duke Energy This cask has one of the highest total heat loads of any DCS system loaded in the U.S.. Using best estimate operational data from the utility, fuel assembly and cask design information from the vendors, and decay heat estimates from Oak Ridge National Laboratory (ORNL), PNNL calculated the maximum cladding temperature of 307?C. This is well below the 400?C regulatory guidance limit.