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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.
K. Tasaka, H. Adachi, M. Sobajima, K. Soda, M. Suzuki, M. Okazaki, M. Shiba
Nuclear Technology | Volume 45 | Number 2 | September 1979 | Pages 121-139
Technical Paper | Reactor | doi.org/10.13182/NT79-A32303
Articles are hosted by Taylor and Francis Online.
To evaluate upper head injection system (UHIS) performance during a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), ten UHIS tests were conducted at the ROSA-II test facility. The experimental results were different from the expected UHIS performance in the following points. First, flashing took place in the upper head and a mixture level was formed before UHIS actuation. Second, emptying of the upper head was observed immediately after UHIS shut off. Third, part of the water which flowed down from the upper head, penetrated into the core and contributed to core cooling at the top part of the core, however, most of the water flowed out through the broken loop hot leg. In the case of higher injection water temperature (∼120°C), the fluid behavior in the pressure vessel differed significantly from the results for the low injection water temperature (∼20°C), and the core cooling was remarkably improved. Therefore, high-temperature UHIS water is recommended for effective core cooling. The results described above are due to the following physical phenomena: