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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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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
H. H. Hummel, Kalimullah, and P. Pizzica
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 440-441
Technical Note | doi.org/10.13182/NSE76-A26845
Articles are hosted by Taylor and Francis Online.
Recalculation of sodium voiding ramp rates in a loss-of-flow accident for a model of a 4000-MW(e) oxide-fueled liquid-metal fast breeder reactor gave results much lower than those found previously by Bleiweis et al. Only a part of this difference could be ascribed to differences in the primary coolant loop model.
