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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.
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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
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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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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.
M. M. R. Williams
Nuclear Science and Engineering | Volume 112 | Number 3 | November 1992 | Pages 215-230
Technical Paper | doi.org/10.13182/NSE92-A29070
Articles are hosted by Taylor and Francis Online.
The physical and mathematical problems associated with radioactive waste disposal have been outlined and discussed. Some of the more important relationships and equations have been derived and explained with a view to showing how techniques developed in conventional reactor physics problems can be applied with great effect to radionuclide transport. We stress in particular the problems associated with radionuclide transport through spatially random media such as fissured and porous rock. Three distinct modeling procedures are presented: (1) the classical advective dispersion equation and its interpretation as a stochastic differential equation, (2) a purely advective approach in which the groundwater velocity and the retardation factor are random functions, and (3) an analogy with neutron transport by regarding motion along fissures and subsequent branching as a pseudo-scattering process. We describe the mathematical methods needed to solve these stochastic problems and include perturbation theory, Novikov’s theorem and the marked Brownian particle. The relationship between the methods and the non-Fickian behavior that results are discussed and used to explain the scale-dependent experimental results for the dispersion coefficient. In general, the paper attempts to be instructive in that several results are presented which are not new, but also creative in that these results are presented in a new light. Two new models are also discussed and their advantages and shortcomings outlined.