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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
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.