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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
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.