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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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
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.
David Garrido (ENSA), Steven Ross (PNNL), Paul E. McConnell, Willaim Uncapher (SNL), Philip Jensen, Nicholas Klymyshyn (PNNL), Sylvia Saltzstein, Ken Sorenson (SNL), Brady Hanson, Ralph Best (PNNL), William Shust (Objective Engineers), Jeff L. England (SRNS), Russ Walker, Ruben Pena (Transportation Technology Center, Inc.)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 72-78
The objective of the shock and vibration testing program is to quantify mechanical loads on fuel assembly components that would occur during normal conditions of transportation (NCT) by various modes. This information will guide materials research and establish a technical basis for review organizations such as the U.S. Nuclear Regulatory Commission (NRC). A significant body of experimental and numerical modeling data exists to quantify loads and failure limits applicable to NCT rail transport, but the data are either out-of-date relative to present day railroad operations and equipment, or are based on assumptions that can only be verified through experimental testing. The summary presented herein represents a collaboration among many stakeholders to define the path for acquiring new data that is needed to validate the assumptions of previous work, validate modelling methods that will be needed to evaluate the mechanical responses of used nuclear fuel that will be transported in the future in large rail casks, and inform material test campaigns on the anticipated range of stresses that will be imposed on nuclear fuel cladding. This work will include full scale testing of a used nuclear fuel cask, cradle, rail car, and surrogate fuel assemblies and will encompass intermodal transloading, heavy-haul truck transport, barge transport, ocean going vessel transport, and rail transport as well as captive track tests. The ultimate goal of this testing will be to close some of the existing knowledge gaps related to the mechanical loads that would be imposed on used nuclear fuel under NCT and inform the experiments and analysis efforts