ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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
Jun 2025
Jan 2025
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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
NextGen MURR Working Group established in Missouri
The University of Missouri’s Board of Curators has created the NextGen MURR Working Group to serve as a strategic advisory body for the development of the NextGen MURR (University of Missouri Research Reactor).
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Wednesday, June 15, 2022|1:00–2:45PM PDT|Redondo
Session Chair:
Nolan Goth
Alternate Chair:
Sheng Zhang
Session Organizer:
W. David Pointer
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Scaled Experiment Design for Transient Heat Transfer in Molten Salt-Cooled Reactor Channels
Omar Ashraf Alzaabi (Univ. California, Berkeley), Per Peterson (Univ. California, Berkeley)
Paper
Numerical Investigations on Hydrodynamic Molten Salt Lubricated Bearings
Yuqi Liu (Univ. New Mexico), Daniel L. Barth (High Temperature System Designs), Adam Burak (Univ. Michigan), Shuai Che (Univ. Michigan), Minghui Chen (Univ. New Mexico)
Design of a High-Temperature Molten-Salt Pump Bearing Test Facility
CFD Analysis of Tritium Removal from Molten Salt Reactors by Sparging Helium Gas Bubbles
Anthony G. Bowers Jr. (Univ. Massachusetts, Lowell), Subash L. Sharma (Univ. Massachusetts, Lowell), Piyush Sabharwall (INL)
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