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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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
R. T. Santoro, R. A. Lillie, R. G. Alsmiller, Jr., J. M. Barnes
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 225-242
Technical Paper | doi.org/10.13182/NSE79-A20145
Articles are hosted by Taylor and Francis Online.
Two- and three-dimensional radiation transport methods have been employed to estimate the nuclear performance of the neutral beam injectors being designed for the Tokamak Fusion Test Reactor. The nuclear heating rates and neutron and gamma-ray energy spectra have been calculated at various locations in a detailed calculational model of the injector using Monte Carlo methods. Calculations have also been carried out using discrete-ordinates methods to obtain estimates of these data in a two-dimensional model of the injector. The two-dimensional calculational procedure was developed as an analytic tool for more cost-efficient scoping and parametric studies of the effects of design changes on the injector performance due to the streaming of 14-MeV neutrons. The nuclear responses and spectra obtained using the two-dimensional calculational model agree with the more definitive data obtained using the three-dimensional model within a factor of ∼5.