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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
W. P. Stinson, L. C. Schmid, R. E. Heineman
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 435-441
Technical Paper | doi.org/10.13182/NSE60-A25741
Articles are hosted by Taylor and Francis Online.
Information about effective neutron temperatures has been inferred from measurements of the ratio of the thermal-fission activity of a Pu239 foil to that of a U235 foil. A discussion of the ratios obtained in various assemblies which were placed in the center of a graphite thermal column is presented. The assemblies were made of natural uranium, lead, or graphite. In some cases the assemblies were surrounded by a layer of water. The experiments were conducted at thermal-column temperatures which ranged from 18 to 640°C. The data obtained in the case of the graphite assembly are used as a calibration of the neutron temperature. To within the accuracy of the experiment, the shape of this calibration curve is the same as the shape obtained from the data of C. H. Westcott. The results, for all other cases, indicate for the range of temperatures investigated that the ratio of the thermal-column temperature to the effective neutron temperature in an assembly varies linearly with the temperature of the thermal column.
