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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.
G. J. Safford, W. W. Havens, Jr., B. M. Rustad
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 433-440
Technical Paper | doi.org/10.13182/NSE59-A25682
Articles are hosted by Taylor and Francis Online.
The absolute value of the total neutron cross section of U235 was measured for neutrons in the energy range 0.000818 to 0.0818 ev for two types of samples, metallic foils and D2O solutions of uranium. Balanced solutions of U235O2(NO3)2 and U238O2(NO3)2 were used to determine the difference between the total cross sections of U235 and U238. This value when combined with the relatively small, known value of the total cross section for U238 gives σT(U235) = 695.0 ± 1.8 barns at 0.0253 ev. The measurements on the metallic U235 foils agreed with the measured total cross section determined from the liquid solution data to better than 1%, yielding σT(U235) = 698.7 ± 4.7 barns at 0.0253 ev. The measured value of the U235 total cross section at 0.00291 ev combined with the scattering cross section, a recent precise value of (1 + α) at 0.00291 ev, and the ratio σf (0.0253 ev)/σf (U235) = 590.8 ± 5.4 barns at the standard neutron energy of 0.0253 ev.
