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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Herbert Bachmann, Ulrike Fritscher, Friedbert W. Kappler, Detlef Rusch, Heinrich Werle, Hans W. Wiese
Nuclear Science and Engineering | Volume 67 | Number 1 | July 1978 | Pages 74-84
Technical Paper | doi.org/10.13182/NSE78-A27238
Articles are hosted by Taylor and Francis Online.
Measured and calculated neutron spectra from a sphere of lithium metal with natural isotopic composition are compared. In the calculations, the investigation is concentrated on the SN method with nuclear data from ENDF/B-III for lithium and from KEDAK 3 for iron. A special partition of the angular coordinate, S19, was introduced to allow for the strong anisotropy of the neutron flux in the radial direction. For the proper treatment of the anisotropic elastic scattering, a new technique for improved, extended, and consistent transport approximation up to T5 is used. These ameliorations being introduced, it is shown that the nonelastic scattering is treated inadequately with respect to the angular and energetic distribution of the outcoming neutrons. The investigation is completed by a comparison of the measured and calculated space-dependent tritium production rate, in which the discrepancy is found consistent with the discrepancy in the neutron spectra. Furthermore, we propose that the 7Li(n,n′α) cross section should be reduced by 15 to 20% with respect to the ENDF/B-III value.