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
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
CLEAN SMART bill reintroduced in Senate
Senators Ben Ray Luján (D., N.M.) and Tim Scott (R., S.C.) have reintroduced legislation aimed at leveraging the best available science and technology at U.S. national laboratories to support the cleanup of legacy nuclear waste.
The Combining Laboratory Expertise to Accelerate Novel Solutions for Minimizing Accumulated Radioactive Toxins (CLEAN SMART) Act, introduced on February 11, would authorize up to $58 million annually to develop, demonstrate, and deploy innovative technologies, targeting reduced costs and safer, faster remediation of sites from the Manhattan Project and Cold War.
D. D. Sood, P. N. Iyer, R. Prasad, V. N. Vaidya, K. N. Roy, V. Venugopal, Z. Singh, M. V. Ramaniah
Nuclear Technology | Volume 27 | Number 3 | November 1975 | Pages 411-415
Technical Paper | Material | doi.org/10.13182/NT75-A24314
Articles are hosted by Taylor and Francis Online.
The feasibility of using plutonium as a fuel in a molten salt reactor has been evaluated by the determination of the solubility of PuF3 in a number of salt compositions containing LiF, BeF2, and ThF4 in the temperature range of interest for such a reactor. An empirical correlation for the solubility of PuF3 as a function of salt composition has been obtained from the solubility data to calculate the solubility of PuF3 in other salt compositions of interest. These data indicate that PuF3 has adequate solubility in salt compositions of interest for a molten salt reactor of either the converter or the breeder type.
