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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
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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February 2025
Latest News
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Chaitanyamoy Ganguly, Parameshwar Venkappa Hegde, Gyan Chand Jain, Uddharan Basak, Radhey Shyam Mehrotra, Sukomal Majumdar, Pradip Ranjan Roy
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 59-69
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A33753
Articles are hosted by Taylor and Francis Online.
Mixed uranium-plutonium monocarbide (MC) with a controlled amount of mixed sesquicarbide (M2C3) will be used as driver fuel for the first time in the world in the fast breeder test reactor (FBTR) at Kalpakkam, India. The mixed-carbide fuel for the FBTR has been developed on the basis of indigenous resources of plutonium and natural uranium and has a plutonium-rich composition [Pu/(U + Pu) = 0.7], The mixed-carbide fuel development and fabrication experience in Trombay is described, highlighting the essential features of the carbide fuel pellet fabrication plant, the carbothermic synthesis of MC from the oxides (UO2 + PuO2), and the sintering of MC.