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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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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.
Josée Perfettini
Nuclear Technology | Volume 115 | Number 2 | August 1996 | Pages 153-161
Technical Paper | Characterization of Radioactive Waste in France / Radioactive Waste Management | doi.org/10.13182/NT96-A35261
Articles are hosted by Taylor and Francis Online.
A neutronic method based on neutron thermalization by hydrogen nuclei is used to measure the moisture content in packages of radioactive waste embedded in hydraulic binders. The two steps of the measurement are (a) acquisition of the neutron characteristics of the embedded waste considered (or of a chemically similar material) and (b) the measurement itself obtained with a neutron moisture meter. The neutron characteristics required are the adsorption and diffusion cross sections ∑a and ∑d for thermal neutrons of the dried material. These two parameters are used to calculate the calibration curve (valid only for the material considered) as follows:N = (α·Ds + β)Hυ + γ·Ds + δ,which allows the counting N of the neutron moisture meter to be converted into free-water content Hv (α, β, γ, and δ are deduced from ∑a and ∑d; Ds is the dry density of the material). The neutron moisture meter (containing a fast neutron source and a thermalized neutron detector) is portable. Measurements are taken at various depths in a core hole made in the package to draw a water profile. The measurements are taken in materials used for waste solidification and in active or inactive packages. The results obtained (free-water content) are in good agreement with those obtained by determining the weight loss at 120°C (the differences between these two measurements are generally ∼10% when the free-water content is ∼20 to 25 %). The water profiles allow one to detect the presence of excessive free water.