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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
R. A. Borrelli, Joonhong Ahn
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 442-464
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A4037
Articles are hosted by Taylor and Francis Online.
A scoping study is presented in order to investigate the potential of bentonite extrusion on radionuclide transport in a water-saturated planar fracture. A coupled mathematical model for an abstracted case describing the mass conservation of radionuclides and bentonite extrusion into the fracture is established to observe the mass transport phenomena due to bentonite extrusion in the fracture domain. Results of numerical simulations are then analyzed in order to interpret the potential importance of extrusion in the near-field rock on the overall performance of the engineered barrier system (EBS). The mathematical model developed in this study for radionuclide migration incorporates spatial and temporal changes in porosity due to movement of bentonite particles. Finite element solutions have been derived for the porosity and for the radionuclide concentration.With a sufficiently strong sorption, the radionuclide is observed to be contained within the region of bentonite extrusion, indicating that radionuclides would be retained within the extrusion region even if the waste canister fails early while bentonite is extruding in fractures. Such results imply the potential of the extrusion region to enhance performance in the EBS and warrant more rigorous modeling studies of this domain.