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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
M. Azam, R. S. Gowda, S. Ganesan
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 320-324
Technical Paper | doi.org/10.13182/NSE06-A2586
Articles are hosted by Taylor and Francis Online.
The relative differential cross section for testing the validity of the Ramsauer model was previously introduced by Azam and Gowda. This quantity for intermediate energy neutron scattering processes is independent of the details of nuclear interaction and depends only on nuclear radius as a parameter. In this paper we use this quantity to predict the neutron total and differential shape-elastic cross sections. We show that, given the radius parameter, by making a measurement of the differential cross section at one angle, the total shape-elastic cross section (and hence the reaction cross section if the total cross section is known) can be determined to a good degree of accuracy. The forward-angle differential shape-elastic cross section is also well predicted. The method is of very general applicability and will be most useful in those situations where model-based fits to these quantities either do not exist or are unreliable for extrapolation/interpolation.