ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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May 2025
Latest News
Dragonfly, a Pu-fueled drone heading to Titan, gets key NASA approval
Curiosity landed on Mars sporting a radioisotope thermoelectric generator (RTG) in 2012, and a second NASA rover, Perseverance, landed in 2021. Both are still rolling across the red planet in the name of science. Another exploratory craft with a similar plutonium-238–fueled RTG but a very different mission—to fly between multiple test sites on Titan, Saturn’s largest moon—recently got one step closer to deployment.
On April 25, NASA and the Johns Hopkins University Applied Physics Laboratory (APL) announced that the Dragonfly mission to Saturn’s icy moon passed its critical design review. “Passing this mission milestone means that Dragonfly’s mission design, fabrication, integration, and test plans are all approved, and the mission can now turn its attention to the construction of the spacecraft itself,” according to NASA.
Christophe Poussin, Alain Holcblat
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 108-121
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A15856
Articles are hosted by Taylor and Francis Online.
Thermal stratification may be responsible for the development of severe cracks in the feedwater line of steam generators in pressurized water reactors, leading Framatome to carry out an experimental program especially dedicated to this problem. This developmental program analyzes the mechanisms and the driving parameters of thermal stratification. It develops and qualifies an antistratification device to prevent thermal stratification at the steam generator feedwater nozzle location. The program also compares on-site measurements with mockup results. The outcome of the experimental program is a qualified helical antistratification device to be installed in the thermal sleeve of the steam generator feedwater nozzle. As required, this device significantly reduces thermal stratification effects in the feedwater system, even in very low feedwater flow conditions.