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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Askar A. Gubaidullin, Bal Raj Sehgal
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 90-92
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT02-A3280
Articles are hosted by Taylor and Francis Online.
A semiempirical correlation for an estimate of crust thickness in a molten pool is presented and validated against published experimental data. The proposed correlation between the dimensionless crust thickness and the Biot and the Prandtl numbers has been developed as [overbar]* = 14.49BiPr -0.074. A scaling methodology is discussed to analyze the thermal resistance of the crust. The results are of interest for the corium melt coolability in a postulated severe accident scenario in a light water reactor.