ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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 Science and Engineering
June 2025
Nuclear Technology
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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.
R. Sanchez, N. J. McCormick
Nuclear Science and Engineering | Volume 83 | Number 1 | January 1983 | Pages 63-71
Technical Paper | doi.org/10.13182/NSE83-A17989
Articles are hosted by Taylor and Francis Online.
Direct and adjoint plane geometry diffusion solutions are combined to provide an inverse method for determining multigroup cross sections and diffusion coefficients; for the equations to work, one group constant for each group must be known. The equations are linear and independent of the slab thickness and require that only the fluxes on the boundaries be measured for a set of experiments with known ingoing currents. The accuracy of the method has been numerically checked using analytical solutions. Another application of the method is to determine the relative concentration of one or more isotopes in a mixture of isotopes whose microscopic cross sections are known.