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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
James M. Taub
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 77-86
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31540
Articles are hosted by Taylor and Francis Online.
The use of pulsed reactors for the evaluation of materials and components has been on the increase and pulsed reactors to handle large components are under consideration. Pulsed reactors currently operate at a 30 to 50 u sec pulse width and a neutron yield of 5 × 1016 fission/pulse; improved capability would move toward even smaller pulse widths and neutron yields in the 1017 fission/pulse range. The gamma phase U—10 Mo alloy with highly enriched uranium has been the fuel alloy used in most pulsed reactors. The fabrication of U—10 Mo alloy fuel plates for the new SPR-III reactor at Sandia Laboratories, Albuquerque, New Mexico, required a detailed review of all processing operations because of the highly enriched uranium and the related criticality considerations. It was necessary to cast the maximum allowable mass of highly enriched uranium (36 kg) in order to make a single fuel plate. The low carbon impurity level specified was obtained with the formulation of a new and highly successful composite coating material for graphite crucibles and molds. The plate distortions which occur in water quenching the alloy from the 950°C gamma phase to room temperature were eliminated by quenching between cold platens in a hydraulic press. Typical mechanical properties obtained on cast, heat treated plates were 930 MPa yield strength, 940 MPa tensile strength, 12.9% elongation in 25.4 mm, and 35.4% reduction in area.