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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.
Aamir Husain
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 66-73
Technical Paper | Chemical Processing | doi.org/10.13182/NT89-A34228
Articles are hosted by Taylor and Francis Online.
A regenerative process involving the use of a dilute solution of nitric (0.5 to 1.0 wt%) and hydrofluoric (0.05 wt%) acids was developed for decontaminating stainless steels (Type 304) to release limits. The solution is regenerated using a strong acid cation exchanger and may eventually be disposed of after processing through a strong base anion exchanger. The waste management aspect of the decontamination is thus limited to the disposal of relatively small volumes of spent cation and anion exchange resins. Application of the acidic reagent for 1 hat 95°C to the tray surfaces of an obsolete irradiated fuel storage basket from Pickering Nuclear Generating Station resulted in the removal of metal exceeding 1 µm and a residual (β,γ) contamination below a target limit of 0.1 µCi/m2. A soak tank system with associated purification, vapor handling, and auxiliary systems is proposed for performing full-scale decontaminations of the baskets.