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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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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
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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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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.
Hans Conrads
Nuclear Science and Engineering | Volume 106 | Number 3 | November 1990 | Pages 299-307
Technical Paper | doi.org/10.13182/NSE90-A29058
Articles are hosted by Taylor and Francis Online.
The properties of dense plasma focus, a point source of fusion neutrons with high flux density, are described and its applications to problems in fusion technology are discussed, including assessment of the performance of electronics and diagnostics in the stream of neutrons behind a breeding blanket, measurement of the concentration of neutron-induced isomeres in the first wall and blanket, and determining radiation-induced damage under pulsed and steady neutron loads. The plasma focus phenomenon is described and the technical details of a device for high repetition rates are given, including the characteristics of the electrical circuits. Scaling the yield for 10- and 13-MeV neutrons in tritium-free discharges is also addressed.