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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Apr 2025
Jan 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Bill would require NRC reporting of nuclear medicine extravasations
Bipartisan legislation introduced into the U.S. House of Representatives earlier this month seeks to close a loophole that currently allows medical patients to be unintentionally exposed to radiation without reporting or disclosure. The Nuclear Medicine Clarification Act of 2025 (H.R. 2541) was introduced into the House by Reps. Don Davis (D., N.C.), Morgan Griffith (R., Va.), and Ben Cline (R., Va.), who said the legislation would improve care and ensure transparency for patients and simplify federal rules coming from the Nuclear Regulatory Commission.
Sunday, July 21, 2024|8:00AM–4:00PM CDT
University Room AB - Cost $99
This workshop will provide an introduction to the fundamentals of fusion neutronics through a combination of theory and simulation exercises to be carried out with OpenMC. OpenMC is a general purpose Monte Carlo neutron and photon transport simulation code. It is capable of simulating 3D models based on constructive solid geometry as well as CAD-based geometries using the DAGMC library. OpenMC was originally developed by members of the Computational Reactor Physics Group at the Massachusetts Institute of Technology starting in 2011 with a specific focus on high performance computing and has now evolved into a community developed code with contributions from many institutions. The specific programming and analysis exercises that will be explored in the workshop include: neutron and photon transport, activation simulations, tritium production, nuclear heating, and shutdown dose rates. All levels of experience with fusion neutronics are welcome. Our only recommendation is that attendees have some experience with the Python programming language.