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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.
H. L. McMurry, G. A. Cazier, R. W. Goin
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 44-48
Technical Paper | doi.org/10.13182/NSE59-A25625
Articles are hosted by Taylor and Francis Online.
For economical operation of the MTR, mixtures of new and used fuel must be distributed so that the required cycle time is met. An equation is derived which expresses the megawatt days possible from a new fuel charge in terms of the known life of the preceding charge, and the change in the initial fuel loading. The equation takes account of effects arising from differences in the initial U235 contents of the fuel assemblies, changes in the equilibrium concentrations of Xe135 and Sm149 during the run, and production of low cross section fission poisons. For certain conditions of common occurrence it reduces to a semi-empirical equation which has been used in the past for calculating fuel loadings. The theory can be used to derive equations for the charge life when fuels other than U235 are used.