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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
EnergySolutions to help explore advanced reactor development in Utah
Utah-based waste management company EnergySolutions announced that it has signed a memorandum of understating with the Intermountain Power Agency and the state of Utah to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta, Utah.
Advances in Thermal Hydraulics (ATH 2024)
Technical Session
Tuesday, November 19, 2024|8:00–9:45AM EST|Coral C
Session Chair:
Subash Sharma (UML)
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AI-Enabled Fuel Temperature Prediction with Digital Visualization Using Heat Pipes in Microreactor Monolith Cores
8:00–8:20AM EST
Ik Jae Jin (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)
Paper
Data Efficiency Assessment of Generative Adversarial Networks for Critical Heat Flux Synthetic Data Generation
8:20–8:40AM EST
Umme Mahbuba Nabila (Univ. Michigan), Linyu Lin (INL), Majdi I. Radaideh (Univ. Michigan)
Probabilistic Bayesian Neural Network (PBNN) for CHF Prediction with Uncertainty in a Uniformly Heated Vertical Tube Using CHF NRC Database
8:40–9:00AM EST
Anadi Mondal (Univ. Massachusetts, Lowell), Subash L. Sharma (Univ. Massachusetts, Lowell)
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