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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Jacob Dobisesky, Joshua Richard, Edward E. Pilat, Mujid S. Kazimi, David M. Carpenter
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 353-377
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-131
Articles are hosted by Taylor and Francis Online.
The primary motivation for using silicon carbide rather than zirconium alloy cladding is its putative improvement in accident resistance, due to slow reactions with water, even at high temperatures. But, fuel management performance will also be an important consideration in its commercial acceptance. Whether backfittable 18- and 24-month cycles can be designed for existing light water reactors, their enrichments, operating characteristics, and fuel costs are questions that the present study undertakes to answer. Also evaluated is the possibility of leveraging silicon carbide's ability to sustain higher fuel duty for increasing power levels and discharge burnups in pressurized water reactors. A preliminary design using fuel rods with the same dimensions as in typical Westinghouse fuel, but with fuel pellets having a 10 vol % central void, has been adopted to mitigate the higher fuel temperatures when silicon carbide is used. This allows design of 18- and 24-month cycles that meet present-day operating constraints on peaking factor, boron concentration, reactivity coefficients, and shutdown margin, while achieving batch average discharge burnups up to 80 MWd/kg U, as well as power uprates of 10% and possibly 20%. Control rod configuration modifications may be required to meet the shutdown margin criterion for the 20% uprate. For nonuprated cores, silicon carbide–clad fuel may have a fuel cost advantage, especially with increasing discharge burnup, provided the fuel manufacturing cost is close to that of Zircaloy tubes. The economics of the fuel cycle also improve with power uprates, as the value of the additional energy generated may substantially exceed the advantage from fuel cost alone.