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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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Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
M. Necati Özişik, H. J. de Nordwall
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 310-319
Technical Paper | doi.org/10.13182/NSE71-A20164
Articles are hosted by Taylor and Francis Online.
The rate, extent, and spatial variation of carbon loss from a graphite cylinder exposed to steam has been calculated as a function of time. The geometrical arrangement considered was a hollow cylinder with a helium-steam mixture on the inside. At the outer boundary either a zero concentration or a zero steam flux may be maintained. The reaction was assumed to be first order. Changes in the rate of carbon removal with time other than those associated with establishing a steady-state steam concentration gradient were not considered. Calculations using constants derived from current experimental work lead one to conclude that the time needed to establish a concentration gradient is insignificant compared with the times for which the hot core of a high-temperature gas-cooled reactor could be exposed to steam accidentally. This conclusion could change if much tighter graphites or more massive sections, equivalent to thicker cylinders in our analysis, were to be used.