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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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Latest News
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Sanjay Krishnarao Sali, Donal Marshal Noronha, Hemakant Ramkrishna Mhatre, Murlidhar Anna Mahajan, Keshav Chander, Suresh Kumar Aggarwal, Venkatarama Venugopal
Nuclear Technology | Volume 151 | Number 3 | September 2005 | Pages 289-296
Technical Paper | Reprocessing | doi.org/10.13182/NT05-A3651
Articles are hosted by Taylor and Francis Online.
A novel methodology has been developed for the recovery of Pu from different types of waste solutions generated during various operations involved in the chemical quality control/assurance of nuclear fuels. The method is based on the precipitation of Pu as ammonium plutonium(III)-oxalate and involves the adjustment of acidity of the Pu solution to 1 N, the addition of ascorbic acid (0.05 M) to reduce Pu to Pu(III), followed by the addition of (NH4)2SO4 (0.5 M) and a stoichiometric amount of saturated oxalic acid maintaining a 0.2 M excess of oxalic acid concentration in the supernatant. The precipitate was characterized by X-ray powder diffraction and thermal and chemical analysis and was found to have the composition NH4Pu(C2O4)23H2O. This compound can be easily decomposed to PuO2 on heating in air at 823 K. Decontamination factors of U, Fe, and Cr determined showed quantitative removal of these ions during the precipitation of Pu as ammonium plutonium(III)-oxalate.A semiautomatic assembly based on the transfer of solutions by suction arrangement was designed and fabricated for processing large volumes of Pu solution. This assembly reduced the corrosion of the glove-box material and offered the advantage of lower radiation exposure to the working personnel.