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
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
DOE on track to deliver high-burnup SNF to Idaho by 2027
The Department of Energy said it anticipated delivering a research cask of high-burnup spent nuclear fuel from Dominion Energy’s North Anna nuclear power plant in Virginia to Idaho National Laboratory by fall 2027. The planned shipment is part of the High Burnup Dry Storage Research Project being conducted by the DOE with the Electric Power Research Institute.
As preparations continue, the DOE said it is working closely with federal agencies as well as tribal and state governments along potential transportation routes to ensure safety, transparency, and readiness every step of the way.
Watch the DOE’s latest video outlining the project here.
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.