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.
Explore membership for yourself or for your organization.
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
UM conducts molten salt experiment
For 2,300 hours, the molten salt pump Shaft Seal Test Facility (SSTF) operated at the University of Michigan’s Thermal Hydraulics Laboratory, according to an article from UM. The large-scale experiment was designed to evaluate shaft seal performance in high-temperature pump systems. Fewer than 10 facilities worldwide have successfully operated fluoride or chloride salts for more than 100 hours using over 10 kilograms of material.
R. E. MacPherson, J. C. Amos, H. W. Savage
Nuclear Science and Engineering | Volume 8 | Number 1 | July 1960 | Pages 14-20
Technical Paper | doi.org/10.13182/NSE8-1-14
Articles are hosted by Taylor and Francis Online.
In order to investigate the design and fabrication problems inherent in compact, high-performance heat exchangers for aircraft nuclear propulsion applications, extensive development testing was done by the ANP Division of the Oak Ridge National Laboratory on bifluid (molten salt-NaK) heat exchangers and on liquid metal (NaK-air) radiators. These test units were prototypes of the heat transfer equipment which was to be used in the Aircraft Reactor Test at ORNL. Five bifluid test loops and one liquid metal test loop were used for performance and endurance testing of these components at simulated reactor operating conditions. The molten salt used was a sodium-zirconium-uranium fluoride mixture of composition NaF—50 mole %, ZrF4—46 mole %, UF4—4 mole %. The NaK used was 56 wt % sodium and 44 wt % potassium. A total of 47,000 hr of operation at 1200–1700°F was accumulated on 18 heat exchangers and 20 radiators. The program demonstrated that the compact heat exchanger geometries tested possessed the performance capabilities and mechanical integrity to meet ART design requirements.