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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
A. P. J. Hodgson, R. W. Grimes, M. J. D. Rushton, O. J. Marsden
Nuclear Science and Engineering | Volume 181 | Number 3 | November 2015 | Pages 302-309
Technical Paper | doi.org/10.13182/NSE14-156
Articles are hosted by Taylor and Francis Online.
Computational models provide a framework through which to predict impurity in-growth in reactor generated radiological sources. However, the energy group structure and methodology used in these codes can have a significant impact on the accuracy of neutron cross sections and, as a result, on the inventory values calculated. The European Activation SYstem II (EASY-II) partitions neutron data in a number of different standard structures and then uses these to generate energy collapsed cross sections for each neutron reaction of interest. How well these single values represent the true neutron environment of the reactor is key to the codes efficacy for evaluating source impurities for use in material attribution. By comparing EASY-II nuclide inventories for cobalt source materials against analytically derived equivalents, these approximations have been shown to have limited impact. However, of the fission applicable standard structures investigated, only XMAS and CCFE were capable of precisely accounting for the differences in the energies required to simulate all the neutron reactions of potential interest to forensic investigations.