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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
ANS's webinar on security in floating and offshore nuclear power
The American Nuclear Society’s Nuclear Nonproliferation Policy Division (NNPD) held a webinar recently exploring the security aspects of floating and offshore nuclear power.
Moderator Shikha Prasad, CEO of Srijan LLC and immediate past chair of the NNPD, began the discussion by recapping the recent exponential growth in the field and its future economic potential before introducing the presenters, each of whom spoke about the work they and their organizations are doing to advance the field.
Below are brief summaries of each speaker’s presentation. To see their thoughts and the ensuing Q&A, click here.
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.