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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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May 2025
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.
Michael R. Jonzen
Nuclear Technology | Volume 45 | Number 1 | August 1979 | Pages 54-67
Technical Paper | Reactor | doi.org/10.13182/NT79-A32285
Articles are hosted by Taylor and Francis Online.
Detailed mass and energy calculations have been used to study the fuel- and power-producing capabilities of a gas-cooled fast reactor and a nonoptimized ignition tokamak fusion-fission hybrid reactor. Equivalent energy inputs and outputs are utilized to evaluate the performance of the reactors. The time to recover reactor inputs, system efficiencies, and lifetime net outputs are compared. Fuel production capabilities of the hybrid are contrasted with those of the gas centrifuge and gaseous diffusion uranium enrichment processes for various ore costs. Results show that fuel- and power-producing hybrid systems can compare favorably with fission breeders and isotope separation systems, particularly when utilized in 233U-fueled symbiotic systems.