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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
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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