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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.
C. L. Schuske, Hugh C. Paxton
Nuclear Technology | Volume 30 | Number 2 | August 1976 | Pages 101-137
Technical Paper | Criticality Array Data and Calculational Method / Chemical Processing | doi.org/10.13182/NT76-A31612
Articles are hosted by Taylor and Francis Online.
The first measurements with arrays of fissile metal were performed at the Los Alamos Scientific Laboratory in 1947 and the first with fissile solutions were performed at the Oak Ridge Critical Experiments Facility in 1949. Since then, there have been many other significant experiments at several U.S. laboratories including, in addition, Rocky Flats, Battelle-Pacific Northwest Laboratory, and the Lawrence Livermore Laboratory. Array tests were the primary sources of data used in developing criticality criteria for fissile-process plants, and they provided the basis for several empirical storage models that are still in use. Some of the experimental data also serve to validate Monte Carlo neutron transport calculations now used extensively by the nuclear safety engineer in the design of storage and processing facilities. The authors feel that there should be additional experimental data for further validation of calculational methods relied upon for criticality safety evaluation. The deficient areas include low-235U-enriched uranium, 233U with and without thorium, and plutonium-uranium mixtures. Also, critical data are lacking for arrays with the concrete reflectors normally found in process-plant environments , and additional experiments on concrete-reflected arrays are needed.