ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Hossein Hashemi-Jozani, Khalil Moshkbar-Bakhshayesh, Soroush Mohtashami, Behzad Rokhbin
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 180-188
Note | doi.org/10.1080/00295450.2023.2224131
Articles are hosted by Taylor and Francis Online.
The computerized simulation of the reactor core is one of the significant steps necessary for designing a nuclear power plant. So far, very suitable Monte Carlo–based codes have been developed (e.g., MCNP, TRIPOLI, KENO, OpenMC, etc.) for the neutronic simulation of the reactor core. In this study, an approach based on Geant4, as an extendable code with the capability to provide a comprehensive reactor core design tool, is developed to calculate the effective multiplication factor (keff) and neutron flux distribution. A combination of the Geant4 code and the NJOY code is applied to calculate the temperature-dependent cross-section library. The C5G7-1D, the Godiva critical facility, and the Jordan subcritical reactor are examined as a benchmarks/case study. The results of the calculation of keff (i.e., relative error < 0.1%) and flux distribution (i.e., relative error <3%) are in very good agreement with the calculation results of the MCNP code and the experimental results. The extensions for the calculation of thermodynamic/thermohydraulic effects as well as the calculation of electron/photon transport and reactor dynamics are under development and will be reported as subsequent results.