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 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
EPRI’s new program aims to strengthen grid resilience
The Electric Power Research Institute has launched a global initiative to prepare future grids by modernizing how the electricity-generating sector detects, anticipates, and responds to emerging risks and manages technological transformation. The nonprofit energy research and development organization intends for the initiative, called Rapid Adaptation of Grid Defense, Analytics, and Resilience (RADAR), to provide a scalable framework, advanced tools, and targeted training for strengthening grid resilience and reliability.
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.
