ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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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February 2025
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Latest News
“Summer time” again? Santee Cooper thinks so
South Carolina public utility Santee Cooper and its partner South Carolina Electric & Gas (SCE&G) called a halt to the Summer-2 and -3 AP1000 construction project in July 2017, citing costly delays and the bankruptcy of Westinghouse. The well-chronicled legal fallout included indictments and settlements, and ultimately left Santee Cooper with the ownership of nonnuclear assets at the construction site in Jenkinsville, S.C.
D. Squarer, A. T. Pieczynski, L. E. Hochreiter
Nuclear Science and Engineering | Volume 80 | Number 1 | January 1982 | Pages 2-13
Technical Paper | doi.org/10.13182/NSE82-A21399
Articles are hosted by Taylor and Francis Online.
In the worst hypothetical accident of a light water reactor (LWR), when all protection systems fail, the core could melt and be converted to a deep particulate bed as a result of molten-fuel-coolant interaction. The containment of such an accident depends on the coolability of the heat generating particulate bed. This paper summarizes published theoretical analyses that may predict bed dry out. In three of the analyses, the fluid flow in the heat generating particulate bed is considered to be laminar (Darcy's law), whereas in one study the fluid flow is solved for both the laminar and the turbulent flow regimes and is affected by capillary forces. The theoretical studies are compared with our recent data and with other recently published data covering a range of parameters that is expected in an LWR accident. An extension of the analysis and the experiments to a mixture of particle sizes is presented. The scaling of the dry out data to high pressures, which may be encountered during the course of an accident, is accomplished by multiplying the experimental bed dryout heat flux by the ratio of dry out flux at pressure to the dryout flux at atmospheric pressure. This ratio was calculated with the theoretical model, which agreed best with the experimental dryout data at atmospheric pressure. Based on the pressures and particle sizes expected in a pressurized water reactor core melt, it is concluded that stable (self-cooled) debris bed formation will occur if sufficient water is available.