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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.
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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
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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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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.
J. W. Boyle, H. A. Mahlman
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 492-500
Technical Paper | doi.org/10.13182/NSE57-A25414
Articles are hosted by Taylor and Francis Online.
Concentrated thorium nitrate solution has been proposed as a blanket material in power-breeder reactors. The radiation stability, especially of the nitrate group, is therefore of considerable importance. The radiation-induced decomposition of thorium nitrate solutions was studied as a function of concentration, type of radiation (fission recoils, pile radiations, gamma rays), temperature, and total energy absorbed. The principal products were H2 and O2 from decomposition of the water, and N2, O2, and oxides of nitrogen from decomposition of the nitrate. Hydrogen yield decreased with increasing thorium nitrate concentration, a behavior similar to that for uranium solutions. Nitrogen yield was independent of temperature, but increased with increasing nitrate concentration and with increasing linear energy transfer along the paths of the ionizing particles. The 100-ev yield of N2 in 2.73 molal solution was 0.06 for fission particle decomposition, 0.006 for pile radiation (mixed fast neutrons and γ rays) and 0.001 for γ radiation alone. The oxide of nitrogen produced with the largest yield was N2O and amounted to about ten per cent of the N2 yield. In-pile autoclave measurements indicated little radiation-induced back reaction of the nitrogen.