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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.
D. M. Clare, W. H. Martin, B. T. Kelly
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 448-458
Technical Paper | doi.org/10.13182/NSE64-A18763
Articles are hosted by Taylor and Francis Online.
An experimental comparison has been made in a hollow fuel element in PLUTO of a number of possible fast-neutron flux monitors with the object of providing such a flux monitor for irradiations in very high flux materials-testing reactors. If 107 mb is adopted as the reference fast-neutron activation cross section of Ni58, the fast-neutron activation cross sections for the reactions Fe54 (n,p) Mn54 and Ti46 (n,p) Sc46 are found to be 73 mb and 8 mb respectively. It is concluded from this experiment that the Fe54 (n,p) Mn54 reaction using iron enriched to 95% Fe54 will be an adequate long-half-life fast-neutron flux monitor for irradiation in the high-flux facilities such as those likely to be used in, for example, BR-2.
