ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Nuclear Science and Engineering
May 2024
Nuclear Technology
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Latest News
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
S. Chaudhury, S. A. Ansari, P. K. Mohapatra, D. M. Noronha, J. S. Pillai, Ashutosh Srivastava, I. C. Pius
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 727-735
Technical Paper | doi.org/10.1080/00295450.2018.1510699
Articles are hosted by Taylor and Francis Online.
Laboratory-scale studies were carried out to develop an analytical methodology for the processing of plutonium-bearing analytical laboratory waste at liter scale using hollow fiber–supported liquid membrane (HFSLM) technique by selective recovery of plutonium from uranium, americium, and other laboratory chemicals. In the first stage, uranium and plutonium were selectively transported from the feed to the receiver phase using 30% tri-n-butyl phosphate/n-dodecane which was used as the carrier in HFSLM. From the thus separated uranium and plutonium mixture, Pu(III) was selectively precipitated as ammonium plutonium(III)-oxalate [NH4Pu(C2O4)2 · 3H2O], leaving most of the uranium in the supernatant solution. A combination of HFSLM method followed by ammonium plutonium–oxalate precipitation is faster, gives lower radiation exposure to working personnel, and generates lesser volume of secondary waste as compared to traditional precipitation/ion-exchange technique. Furthermore, the present methodology signifies its importance in providing a very good yield of Pu recovery (>99%) from waste solution.