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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.
Joseph P. Roberge, Vance L. Sailor
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 502-504
Technical Paper | doi.org/10.13182/NSE60-A25757
Articles are hosted by Taylor and Francis Online.
The total cross section of Lu176 was measured over the range of neutron energies from 0.02 to 0.25 ev. The data were taken with a sample enriched to 70.2% in Lu176. The resonance at 0.142 ev in Lu176 was fitted to a Breit-Wigner single-level formula by the method of shape analysis. Parameters are presented for computing the activation cross section as a function of neutron energy over the region of measurement.
