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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
V. G. Molinari, R. Simonini
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 560-565
Technical Note | doi.org/10.13182/NSE78-A27190
Articles are hosted by Taylor and Francis Online.
The problem of the spatial variation of thermal-neutron fluxes is investigated in the framework of energy-dependent diffusion theory. Neutron flux is expanded here in terms of Laguerre polynomials in energy, weighted with a local Maxwellian distribution in which the neutron temperature depends on the space variable. The method proposed is applied to the diffusion of thermal neutrons in moderating systems with a nonuniform temperature profile.
