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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.
Marie-Louise Pointud, Pierre Chenebault
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 494-500
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31909
Articles are hosted by Taylor and Francis Online.
Radioactive fission gas release from coated particles containing UO2 or (Th-U)O2 fuel kernels was studied by taking into account the following parameters: (a) porosities of kernels and materials surrounding them, (b) irradiation temperature, (c) burrnup, and (d) thermal neutron flux. The main results follow. First, the structure of the kernels is modified during irradiation and, consequently, the mechanism and rate of fission gas release vary. Second, for a dense fuel, released activity results from recoil species ejected by the external surface of the kernel and reemitted from the surrounding porous carbon. Finally, for an initially porous fuel or for a heavily irradiated dense fuel, recoil atoms reemitted from the internal open porosity of the kernel and atoms ejected by knockout give the most important contributions to the release.