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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!
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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
H. Austregesilo, T. Hollands (GRS)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 746-754
The thermal-hydraulic system code ATHLET is one main component of the German code package AC2, developed at GRS for comprehensive analyses of nuclear power plants under design basis and beyond design basis accident conditions. In the frame of code validation, five of the eight experiments performed in the German integral test facility PKL within the OECD/NEA joint project PKL-3 have been selected for the evaluation of code capabilities. One main focus has been the simulation of station blackout (SBO) scenarios. Calculation results show that ATHLET can adequately reproduce the main experimental phenomena, including pressure and temperature evolutions, coolant distribution in the primary circuit, and restart of natural circulation in the loop with emergency feedwater injection. Another main contribution to code validation was the simulation of small break loss-of-coolant (SBLOCA) tests. These tests have been designed as counterpart tests to experiments previously performed at the Japanese LSTF facility, providing a sound indication of the scalability of code results.