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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
P. Ihle
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 206-219
Technical Paper | doi.org/10.13182/NSE84-A18578
Articles are hosted by Taylor and Francis Online.
The results of flooding experiments with blocked arrays (FEBA) are presented, a program performed at Kernforschungszentrum Karlsruhe within the framework of the Project Nuclear Safety (PNS). Experiments performed out of pile show that coolant channel constrictions of up to 90% do not lead to significant core coolability problems during reflood. This is even true for low water injection rates corresponding to a flooding velocity of 2 cm/s for the cold bundle. The results of the thermal-hydraulic experiments cover rather widely the cladding temperature range below 1000°C. However, outlining the total range of heat transfer conditions in severely damaged rod bundle geometries, investigations performed within the framework of the PNS are mentioned as well. They provide information about the condition of rod bundles being exposed to temperatures of up to 2000°C prior to reflood.