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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Thomas J. Downar, Jen-Ying Wu, John Steill, Raghunandan Janardhan
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 133-150
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35320
Articles are hosted by Taylor and Francis Online.
High-fidelity simulation of nuclear reactor accidents such as the rupture of a main steam line in a pressurized water reactor (PWR) requires three-dimensional core hydrodynamics modeling because of the strong effect channel cross flow has on reactor kinetics. A parallel nested Krylov linear solver was developed and implemented in the RETRAN-03 reactor systems analysis code to make such high-fidelity core modeling practical on engineering workstations. Domain decomposition techniques were also applied to the RETRAN-03 solution algorithm and demonstrated using a distributed memory parallel computer. Applications were performed for a four-loop Westinghouse PWR steam-line-break accident, and performance improvements of over a factor of 30 were achieved for models with 25 flow channels in the core. Larger models (e.g., 104-core channels), previously inaccessible because of memory limitations, were also solved with practical execution times.