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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
KALMAN SHURE, PAUL A. ROYS
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 170-180
Technical Paper | doi.org/10.13182/NSE57-A25385
Articles are hosted by Taylor and Francis Online.
The thermal neutron flux in a water medium from a source disk containing water irradiated in the Materials Testing Reactor has been measured using a BF3 detector. Neutrons from N17 and photoneutrons from N16 gamma rays have been observed. The radial distribution of thermal neutrons from an isotropic point source of N17 neutrons in a water medium out to 35 cm has been deduced, and has been compared with a theoretical calculation of the distribution based on Holte's values of the collision density at 1 ev from a point isotropic source of 1-Mev neutrons. From the results of this experiment and Holte's distribution, the square of the diffusion length plus the age from 1 ev to thermal energies, has been calculated to be 8.2 cm2. This value is in reasonable agreement with previously reported measured values.