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.
L. M. Howe, R. E. Jervis, T. A. Eastwood
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 185-189
Technical Paper | doi.org/10.13182/NSE12-2-185
Articles are hosted by Taylor and Francis Online.
Aluminum-gold alloy wire of very uniform cross section and composition has been made for the preparation of neutron flux monitors. Because the wire is uniform, a device to cut it into pieces of equal length can be used for the rapid preparation of flux monitors and the need to weigh individual monitors can thus be avoided. Homogeneity of composition was achieved mainly by rolling and annealing, and the effectiveness of each step was assessed by neutron-activation analysis. The gold content of the final product (wire 0.018 in. diameter) was also determined by activation analysis and was found to be 0.0985 ± 0.0020 atom %. Thermal-neutron self-shielding in this wire is negligible and cadmium ratio experiments show that resonance-neutron self-shielding amounts to about 2.5%.