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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Bret Patrick van den Akker (ORNL)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 615-621
We present the analytical solution to the one-dimensional radionuclide transport equation in Laplace transform space. Our model accommodates an arbitrary-length decay chain, an arbitrary combination of host rocks (i.e., an arbitrary combination of multiply fractured and porous transport segments), and a flexible source term (i.e., an arbitrary time-dependent release mode at the entrance point to the series of transport segments). The Laplace transformed analytical solution can be numerically inverted to obtain the time-dependent concentration of the radionuclides of interest at an arbitrary down gradient location. This represents an extension of the previously1 developed model to include the feature of hydrodynamic longitudinal dispersion. This additional feature is important because hydrodynamic dispersion is known to reduce the time of first arrival in radionuclide transport models. Increased fidelity in transport pathway calculations is important for reliable performance assessment for the geological disposal of spent nuclear fuels.