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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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 Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Uncertainty contributes to lowest uranium spot prices in 18 months
A combination of plentiful supply and uncertain demand resulted in spot pricing for uranium closing out March below $64 per pound, with dips down to about $63.50 during mid-March—the lowest futures prices in 18 months, according to tracking by analysis firm Trading Economics. Spot prices have also fallen steadily since the beginning of 2024. Meanwhile, long-term prices have held steady at about $80 per pound at the end of March, according to Canadian front-end uranium mining, milling, and conversion company Cameco.
Masayuki Tokitani, Yukinori Hamaji, Yutaka Hiraoka, Yuki Hayashi, Suguru Masuzaki, Hitoshi Tamura, Hiroyuki Noto, Teruya Tanaka, Tatsuya Tsuneyoshi, Yoshiyuki Tsuji, Gen Motojima, Hiromi Hayashi, Takanori Murase, Takeo Muroga, Akio Sagara, Tomohiro Morisaki
Fusion Science and Technology | Volume 79 | Number 6 | August 2023 | Pages 651-661
Research Article | doi.org/10.1080/15361055.2023.2176184
Articles are hosted by Taylor and Francis Online.
A novel method, called Advanced Multi-Step Brazing, was developed to fabricate a new type of divertor heat removal component with W armor and an oxide-dispersion-strengthened copper (GlidCop®) heat sink in the initial phase of our work. Later, a new type of divertor heat removal component, which has a rectangular-shaped cooling channel with a V-shaped staggered-rib structure in the GlidCop heat sink, was developed. This new component showed an extremely high heat removal capability during a ~30 MW/m2 steady-state heat loading condition in our previous work. In this work, the new component was installed in the divertor strike position of the Large Helical Device and exposed to neutral beam injection–heated plasma discharges with 1180 shots (~8000 s) in total. Though submillimeter-scale damage, such as unipolar arc trails and microscale cracks, was identified on the W surface, the extremely high heat removal capability did not show any sign of degradation over the experimental period. On the other hand, remarkable sputtering erosion and redeposition phenomena, due to the strong influx of the divertor plasma, was confirmed on the W armor.
