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
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
N. Levitz, D. E. Grosvenor, S. Vogler, F. G. Teats, N. Quattropani
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 60-63
Technical Note | Chemical Processing | doi.org/10.13182/NT73-A31334
Articles are hosted by Taylor and Francis Online.
A continuous fluidized-bed process for the conversion of uranium/plutonium nitrates to oxides is under development to facilitate the recycle of plutonium in the nuclear fuel cycle. The basic process consists of two steps, each performed in a separate fluid-bed reactor: (a) codenitration at 375°C of uranyl nitrate-plutonium nitrate solutions to a UO3-PuO2 powder form, and (b) reduction of the UO3-PuO2 with hydrogen at 600°C to form UO2-PuO2. Pilot-plant denitration studies with uranyl nitrate-plutonium nitrate solutions containing uranium/plutonium ratios of 50 and 4, and plutonium nitrate solution alone are described, as well as reduction of UO3-PuO2 powder. Examination of the UO3-PuO2 denitration product by autoradiographic and electron microprobe techniques showed that the PuO2 was distributed in the UO3 matrix with a high degree of homogeneity. The conversion process appears to be applicable over the entire range of uranium-plutonium concentrations and for plutonium nitrate alone. The suitability of this product for the fabrication of fuel pellets is being studied in cooperation with nuclear fuel manufacturers.