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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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Fusion Science and Technology
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.
Jean Johner
Fusion Science and Technology | Volume 59 | Number 2 | February 2011 | Pages 308-349
Technical Paper | doi.org/10.13182/FST11-A11650
Articles are hosted by Taylor and Francis Online.
The HELIOS zero-dimensional code (Version 1.0) is described in detail in the case of deuterium-tritium (D-T) plasmas.The part of the code described solves in a self-consistent way the thermal equilibrium equation of a D-T thermonuclear plasma coupled to the conservation equation of the helium ash with a He*/E = const. constraint.Prominent features of the modeling are the following: description of any type of last closed magnetic surface (LCMS) by means of four portions of conics; exact closed form expressions for the poloidal surface, plasma volume, plasma surface, and LCMS length; exact surface and volume integration (for arbitrary aspect ratio) in the approximation of magnetic surfaces similar to the LCMS; parabolic type density profile and two-parameters temperature profile, both with pedestals and finite values at the separatrix; line radiation of light impurities calculated from tabulated radiative power loss functions; scalings for the pedestal temperature, L-H transition, and confinement time; modeling for the divertor thermal load; self-consistent radial build modeling for the plateau duration calculation; and detailed power plant thermal balance.Applications to ITER and DEMO operation and to inductive reactor design are given.
