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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Texas-based WCS chosen to manage U.S.-generated mercury
A five-year, $17.8 million contract has been awarded to Waste Control Specialists for the long-term management and storage of elemental mercury, the Department of Energy’s Office of Environmental Management announced on November 21.
D. V. Yurov, S. A. Brednikhin, S. A. Frolov, S. I. Lezhnin, V. V. Prikhodko, Yu. A. Tsidulko
Fusion Science and Technology | Volume 63 | Number 1 | May 2013 | Pages 313-315
doi.org/10.13182/FST13-A16939
Articles are hosted by Taylor and Francis Online.
Budker Institute of Nuclear Physics SB RAS together with Nuclear Safety Institute RAS is working on a hybrid system with a neutron source based on the gas-dynamic trap (GDT) and sub-critical blanket for incineration of high-activity long-lived radioactive wastes.This report gives an overview of recent results obtained in collaborative development of modeling tools for the described system. Particularly, DOL code was created for the source plasma parameters calculation, NMC code was applied to model neutron transport processes and NMC+ module was developed for burnup calculations. The codes are shortly described in the article. Validation results are also presented.