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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.