ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
IAEA program uses radioisotopes to protect rhinos
After two years of testing, the International Atomic Energy Agency and the University of the Witwatersrand in Johannesburg, South Africa, have begun officially implementing the Rhisotope Project, an innovative effort to combat rhino poaching and trafficking by leveraging nuclear technology.
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.