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.
Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Oct 2024
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Nuclear Science and Engineering
November 2024
Nuclear Technology
Fusion Science and Technology
Latest News
New edition of IAEA’s Climate Change and Nuclear Power available
The 2024 edition of Climate Change and Nuclear Power has been released by the International Atomic Energy Agency. The 99-page report focuses on the need for a significant increase in investment to achieve goals for expanding nuclear power.
The report: According to the IAEA, the report delves into the financing of nuclear projects as ambitious climate targets draw nearer. It also explores the imperative for financial frameworks to help nuclear energy become a cornerstone of global decarbonization efforts and highlights the challenges and best practices in financing nuclear projects.
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.