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Division Spotlight
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.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
Karen A. Miller, Martyn T. Swinhoe, Stephen Croft, Takayuki Tamura, Shun Aiuchi, Akio Kawai, Tomonori Iwamoto
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 98-105
Technical Paper | doi.org/10.13182/NSE12-43
Articles are hosted by Taylor and Francis Online.
As new uranium enrichment plants are proposed and come online worldwide, interest in using neutron methods for uranium hexafluoride (UF6) cylinder assay has been growing; however, large discrepancies exist in published F(α,n) yields from uranium isotopes. Uncertainties in these data are propagated through the analysis of every UF6 measurement and have implications for safeguards conclusions drawn from them. In this paper, a value for the specific F(α,n) yield in UF6 from 234U is calculated from measurements of 30B cylinders containing bulk UF6 at the Rokkasho Enrichment Plant in Japan. The measurements were taken using the Uranium Cylinder Assay System. The yield was derived by combining the cylinder measurements with detailed Monte Carlo modeling, known isotopic composition, and inversion analysis. We calculated the 234U neutron emission rate in UF6 to be (474 ± 21) n/s·g−1 with a 68% confidence level. The results obtained in this study will help enable an important class of nondestructive assay instruments to be applied with greater confidence and accuracy.
