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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Masatoshi Kondo et al.
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 190-194
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8900
Articles are hosted by Taylor and Francis Online.
Molten salt LiF-BeF2 (Flibe) is one of candidates for self-cooled tritium breeder in fusion blanket system. The Ni based alloys of Hastelloy C-276 (6.28Fe, 15.67Cr, 0.42Mn, 15.83Mo, 3.34W, Ni as balance), Inconel 600(7.02Fe, 15.75Cr, Ni as balance) and Inconel 625 (4.12Fe, 21.94Cr, 9.10Mo, Ni as balance) are candidates of structural material of blanket loop components at down stream. Corrosion characteristics of these alloys were investigated by corrosion test in static Flibe at 500°C and 600°C for 1000 hours. The corrosion rates were estimated from the weight losses of specimens, and those of Hastelloy C-276, Inconel 600 and Inconel 625 in Flibe at 600°C were 3.4m/year, 2.8m/year and 1.1m/year, respectively. The mass balance between the weight losses of specimens and the increase of impurity in Flibe by the exposure was investigated, and it was found that the corrosion was mainly caused by the depletion of Cr from the alloys. The corroded surface had high Ni concentration after the Cr depletion by corrosion, and this is expected to be corrosion resistant in Flibe.