ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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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.
Masaaki Uchida, Michio Ichikawa
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 33-44
Technical Paper | Fuel | doi.org/10.13182/NT80-A32554
Articles are hosted by Taylor and Francis Online.
Three Zircaloy-clad UO2 test fuel rods were irradiated at 50 kW/m to a burnup of 15 000 MWd/MTU with an in-pile rod diameter scanning device, and cladding deformations were measured at various power and bumup levels. Major mode of deformation was ridging at pellet interface positions. Magnitude and relevant power levels for various modes of cladding deformation were found to be strongly dependent on initial pellet-cladding gap size. During the first approach to power, smaller gap size caused larger cladding deformation; however, the effect was reversed at higher burnup. Cladding diametral deformation was found to be dictated not only by local thermal expansion of a single pellet, but also by long-range axial force in the pellet stack. In the first power cycle, cladding deformations caused by power ramp were found to decrease during subsequent power holding, but their rate was much reduced at high burnup.