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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Excelsior University student section awarded community education grant
The American Nuclear Society Student Section at Excelsior University in Albany, N.Y., was awarded a $5,000 grant from the ANS Student Section Strategic Fund initiative for its program, Empowering Tomorrow’s Nuclear Innovators: A Collaborative Approach to Nuclear Technology Education and Awareness.
Alexis Maldonado, Christopher Perfetti
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2086-2098
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2162782
Articles are hosted by Taylor and Francis Online.
When designing experiments for full-scale reactor systems, the Monte Carlo N-Particle® and Whisper codes can be used to create neutronic models and compare the similarity of two nuclear systems via correlation coefficients for , the effective multiplication factor. This paper applies this framework to a conceptual heat pipe yttrium-hydride-moderated microreactor system and experiments, but the method can be applied generally to any nuclear reactor design. The framework is intended as a supplement to other neutronics/thermal/multiphysics analyses and provides an objective method to measure the neutronic similarity of two systems. By analyzing the shared nuclear data uncertainty, as well as sensitivity to nuclear data over all neutron energies, highly informative experiments can be designed to aid in the development of microreactor and other advanced reactor technologies and systems.