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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
Ching-Hor Lee, Shi-Ping Teng
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 67-78
Technical Paper | Waste Management Special / Radioactive Waste Disposal | doi.org/10.13182/NT93-A34768
Articles are hosted by Taylor and Francis Online.
An analytical solution covering the entire range of sorption properties of rock has been derived for the migration of radionuclides along a discrete fracture in a porous rock matrix. The analysis takes into account the advective transport in the fracture, longitudinal hydrodynamic dispersion in the fracture, molecular diffusion from the fracture into the rock matrix, adsorption within the matrix, and the radioactive decay. For adsorption of radionuclide within the matrix, the effects of no sorption, linear nonequilibrium sorption, and linear equilibrium sorption are integrated into a generic transient analytical solution. Based on certain assumptions, the problem can be formulated into two coupled one-dimensional transport equations: one for the fracture and another for the porous matrix in a direction perpendicular to the fracture axis. The general solution is of a single semi-infinite integral form that can be evaluated by Gaussian quadrature. The results indicate that the assumption of equilibrium sorption within the rock results in underestimation of the concentration profile along the fracture in the early stages of migration. It is worth noting that the concentration profile of the nonequilibrium sorption case is slightly smaller than that of the equilibrium sorption case after a certain time. However, the profiles eventually approach the same value. It is also confirmed that the porosity of rock strongly affects radionuclide transport in a fracture.