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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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 Technology
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.