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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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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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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.
R. A. Schrack, O. A. Wasson,D. C. Larson, J. K. Dickens, J. H. Todd
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 352-362
Technical Paper | doi.org/10.13182/NSE93-A24044
Articles are hosted by Taylor and Francis Online.
Relative cross-section measurements for the 10B(n, α1γ)7Li reaction were made using the Oak Ridge Electron Linear Accelerator Laboratory neutron source. The cross sections were measured by observing the 478-keV photon using an intrinsic germanium detector. The neutron flux was monitored with a high-efficiency plastic scintillator. Monte Carlo calculations were used to provide multiple-scattering and neutron-attenuation corrections to the data. The measured cross sections differ as much as 40% from the ENDF/B-VI evaluation for incident neutron energies greater than 1.5 MeV.
