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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
A. Shrivastava, M. Makwana, P. Chaudhuri, E. Rajendrakumar
Fusion Science and Technology | Volume 65 | Number 2 | March-April 2014 | Pages 319-324
Technical Paper | doi.org/10.13182/FST13-658
Articles are hosted by Taylor and Francis Online.
In fusion DEMO reactors, the blanket requires lithium-containing ceramics as the tritium breeder material. Lithium metatitanate (Li2TiO3) is being considered as a promising tritium breeding material for thermonuclear fusion reactors because of its reasonable lithium atom density, prominent tritium release rate at low temperatures, low activation characteristics, low thermal expansion coefficient, high thermal conductivity, etc. Li2TiO3 will be used in the Indian Lead-Lithium–Cooled Ceramic Breeder concept to be tested in ITER. Li2TiO3 powder has been synthesized by the solution-combustion technique using a less expensive precursor of titanium, i.e., titanium dioxide (TiO2), at Institute for Plasma Research. Titanium oxynitrate [TiO(NO3)2] and lithium carbonate (Li2CO3) with citric acid fuel are used as the raw materials. The combustion reaction was carried out at citrate-to-metal ratios of 0.8 to 1.5, as well as for various pH values ranging from 1 to 5. Citric acid was used as a fuel material for the reaction. Calcination of the powder was carried out at 600°C. The powders were characterized for phase purity, grain size, and surface area using X-ray diffraction, scanning electron microscopy, and a Brunauer-Emmett-Teller surface area analyzer. Finally, Li2TiO3 pebbles were prepared by extrusion followed by spheronization with a diameter range from 1 to 1.5 mm. The details of the powder systemization, pebble formation, and their various characterizations are discussed in this paper.