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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2021 Student Conference
April 8–10, 2021
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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
November 2020
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ANS webinar to focus on low-dose radiation risk
Join ANS on Thursday, January 21, at noon (ET) for a Q&A with an expert panel as they discuss how to communicate about the risk of low-dose radiation. “Talking About Low-dose Radiation Risk” is a free members-only event that serves as a follow-up to the “Risky Business” President’s Session that took place during the ANS Virtual Winter Meeting last November. The session will take a deeper dive into the many questions generated from the thought-provoking discussion.
Register now to attend the webinar.
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
dx.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.