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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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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.
A. Patra, S. Saha Ray
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 103-109
Technical Note | Reactor Safety | doi.org/10.13182/NT13-148
Articles are hosted by Taylor and Francis Online.
This technical note introduces a numerical procedure that is efficient for calculating the solution for the fractional order nonlinear neutron point-kinetics equation in nuclear reactor dynamics. The explicit finite difference method (EFDM) is applied to solve the fractional order nonlinear neutron point-kinetics equation with Newtonian temperature feedback reactivity. This nonlinear neutron point-kinetics model has been analyzed in the presence of temperature feedback reactivity. The numerical solution obtained by EFDM is an approximate solution that is based on neutron density, precursor concentrations of multigroup delayed neutrons, and the reactivity function. The method is investigated using experimental data, with given initial conditions along with Newtonian temperature feedback reactivity. From the computational results, it can be shown that this numerical approximation method is straightforward and effective for solving fractional order nonlinear neutron point-kinetics equations. Numerical results citing the behavior of neutron density for different types of fractional order are presented graphically.
