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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.
Ivars Neretnieks
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 110-115
]Technical Note | Radioactive Waste Management | doi.org/10.13182/NT83-A33238
Articles are hosted by Taylor and Francis Online.
In a repository for high-level nuclear waste in bedrock that may carry water, the waste will eventually come in contact with water. Radionuclides will dissolve in the water and migrate away from the repository. In crystalline rock in Sweden, the waters at repository depths are reducing. Many of the important radionuclides, e.g., neptunium, uranium, and technetium, have very low solubilities under these conditions (parts per billion levels). The solubility will considerably limit the transport of these species. If by some means the conditions were to change from reducing to oxidizing, the solubility of these species would increase very much, in some cases by 4 to 6 orders of magnitude. Under such circumstances, these nuclides would escape much faster. We have investigated one possible way in which the redox conditions might change, i.e., spent fuel has a considerable alpha activity, which may radiolyze water and produce oxidizing agents such as hydrogen peroxide. The hydrogen peroxide will make the water oxidizing. The compensating factor is ferrous iron in the bedrock. In the investigation of the interaction of these two species, a con-ceptional and a mathematical model is developed describing the movement of the redox front downstream of a repository. A sample calculation based on minimum measured ferrous iron contents in the bedrock and computed (conservatively on the high side) hydrogen peroxide production shows that the redox front could move several tens of metres downstream in the million-year perspective. The rate of radiolysis would decrease considerably if the spent fuel is not wetted to the high degree assumed in the calculations. The results in the sample calculation should be seen as maximum values for the type of repository considered