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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
G. Ferran, W. Haeck, M. Gonin
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 285-301
Technical Paper | doi.org/10.13182/NSE14-64
Articles are hosted by Taylor and Francis Online.
This paper describes in detail a new method to calculate the integral that appears in the expression of cross-section Doppler broadening. This method is based on a Fourier transform and seems quite promising as our tests suggest it is able to reach any required precision within a reasonable amount of calculation time. Another method to calculate Doppler-broadened cross sections based on Gauss quadrature will be presented, even if it requires too much computation time to be of practical use. Both methods have been implemented in a new nuclear data-processing software called GAIA, which is currently under development at the French Institut de Radioprotection et de Sûreté Nucléaire. Results of the comparison of the broadened cross sections obtained with the GAIA methods and with the NJOY processing system are discussed in the paper.
