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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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Nuclear Technology
Fusion Science and Technology
May 2025
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.
Teruya Tanaka, Hiroyuki Noto, Fuminobu Sato, Yoshimitsu Hishinuma, Hiroyuki A. Sakaue, Masahito Yoshino
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 1076-1083
Technical Paper | doi.org/10.1080/15361055.2019.1658039
Articles are hosted by Taylor and Francis Online.
To examine the impact of nuclear transmutation in K-type and N-type thermocouples on temperature measurements in a fusion reactor, thermocouples with altered compositions were fabricated, and their responses were obtained at up to 800°C. The compositions of the thermocouples were altered according to transmutation calculations simulating the 3.5-, 4.6-, and 7-year use at the first wall and 40-year use at the front surface of the radiation shield. Comparison of the responses with commercial thermocouples at 800°C showed that the K-type and N-type thermocouples with altered composition simulating the 7-year use at the first wall indicate 20% to 25% lower temperatures. In this condition, the weight ratio of additive powders for simulation of transmuted elements was ~3%. The differences of responses between the commercial thermocouples and thermocouples simulating transmutation are dependent on the weight ratio of the additive powders. The present data could be used for estimation of response degradation of thermocouples used for long-term operation in a fusion reactor.