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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
October 2025
Latest News
A wave of new U.S.-U.K. deals ahead of Trump’s state visit
President Trump will arrive in the United Kingdom this week for a state visit that promises to include the usual pomp and ceremony alongside the signing of a landmark new agreement on U.S.-U.K. nuclear collaboration.
Keshav Chander, Bharatkumar N. Patil, Jayshree V. Kamat, Nandakumar B. Khedekar, Remani B. Manolkar, Surendranath G. Marathe
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 69-74
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A34010
Articles are hosted by Taylor and Francis Online.
Direct dissolution of uranium carbide was found to be very effective when it was refluxed with an 18 M H2SO4‾15 M HNO3 (1:1) mixture. Clear solutions could be obtained within 1 h. Uranium-plutonium carbide, as well as PuO2 could also be dissolved in 1 to 2 h in the same way. Other nuclear materials, UO2 + C and UO2 + PuO2 + C, needed longer duration for complete dissolution. When the proportion of H2SO4 in the H2SO4‾HNO3 mixture was increased to 2:1, these materials also dissolved within 2 h. Quantitativeness of the dissolution was checked by the potentiometric determination of uranium and/or plutonium contents in these solutions. The results were in good agreement (±0.5%) when compared with the values obtained by the well-established dissolution method. During the fabrication of fuel (plutonium-rich mixed carbide) for the fast breeder test reactor, a large number of fuel samples were analyzed by using the above method of dissolution for the chemical quality control. Presuming the possibility of formation of small amounts of oxalic and mellitic (benzene hexacarboxylic) acids during the process of dissolution of carbides, the effect of the presence of these organic species on the potentiometric determination of uranium and plutonium was studied.