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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.
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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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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.
Sal B. Rodriguez, Randall O. Gauntt, Randy Cole, Katherine McFadden, Fred Gelbard, Len Malczynski, Billy Martin, Shripad T. Revankar, Karen Vierow, Dave Louie, Louis Archuleta
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 752-755
Technical Paper | The Technology of Fusion Energy - Nonelectric Applications | doi.org/10.13182/FST07-A1580
Articles are hosted by Taylor and Francis Online.
A hypothetical Z-Inertial Fusion Energy (IFE) plant was coupled to a sulfur iodine (SI) thermochemical cycle using a new version of MELCOR called MELCOR-H2. MELCOR-H2 was designed to model nuclear reactors that are coupled to thermochemical plants for the production of electricity and hydrogen.The Z-IFE input model consisted of three major system components - a fusion heat source control volume with several types of boundary conditions, an SI loop, and a Brayton secondary system. The components were coupled in order to investigate system feedback and hydrogen production. The input model was modified so that various parametric studies could be conducted. Particular emphasis was placed on plant operating temperature and maximizing hydrogen production.This paper summarizes the results of the SI system model as it was driven by temperature changes in the primary circuit that simulated those that would occur in a Z-IFE driven reactor.