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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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 consortium to address industry need for nuclear heat and power
Hoping to tackle a growing global demand for energy, The Open Group, a vendor-neutral technology and standards membership organization, has announced the formation of the Industrial Advanced Nuclear Consortium (IANC) to collaborate on finding advanced nuclear energy solutions to serve industrial customers.
D. W. Glasgow, F. O. Purser, H. Hogue, J. C. Clement, K. Stelzer, G. Mack, J. R. Boyce, D. H. Epperson, S. G. Buccino, P. W. Lisowski, S. G. Glendinning, E. G. Bilpuch, H. W. Newson, C. R. Gould
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 521-533
Technical Paper | doi.org/10.13182/NSE76-A14488
Articles are hosted by Taylor and Francis Online.
A fast-neutron time-of-flight spectrometer has been constructed for the purpose of measuring neutron differential cross sections of interest to the controlled thermonuclear reactor (CTR) program. The experimental facility provides the capability of measuring scattering cross sections of a few mb/sr to ∼5% absolute accuracy in the energy range from 6 to 15 MeV. Source neutrons are provided by the D(d,n)3He reaction. Scattered neutrons are detected at 28 angles between 25 and 160 deg in a massively shielded NE218 liquid scintillator located 4 m from the scattering sample. Absolute cross sections are obtained by normalizing to n-p scattering. Differential elastic and inelastic scattering cross sections are reported for 8.97-, 9.19-, 9.55-, 9.96-, 10.21-, 10.69-, 10.96-, 11.16-, 11.73-, 11.96-, 12.44-, 12.95-, 13.95-, 14.43-, and 14.93- MeV neutrons incident upon high-purity carbon. Monte Carlo simulation has been used to correct for finite source and sample effects. These data partially fill the 9- to 15-MeV gap in the carbon elastic and inelastic scattering data set required for the CTR program.