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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Latest News
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Byung-Ho Lee, Yang-Hyun Koo, Dong-Seong Sohn
Nuclear Technology | Volume 127 | Number 2 | August 1999 | Pages 151-159
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A2991
Articles are hosted by Taylor and Francis Online.
A model for rim porosity that takes into account the effect of overpressurization on rim pores is proposed for high-burnup UO2 fuel. It is based on the assumption that all the fission gases produced are retained in rim pores, and the threshold pellet average burnup required for the formation of the rim region is 40 MWd/kg U. In addition, a thermal conductivity correlation is proposed that uses the rim porosity model developed. This correlation for the rim region considers both degradation of thermal conductivity with burnup across the fuel pellet and additional degradation at the pellet rim due to very high porosity. To calculate the temperature profile across the fuel pellet where the rim region is formed, the present correlation for the rim region is combined with the HALDEN, MATPRO, and SIMFUEL correlations for thermal conductivity for the fuel interior region where the rim feature does not exist. Application of the present correlation to the measured HALDEN fuel centerline temperature (Nuclear Energy Agency public database IFA-562) shows that good agreement between the calculated and measured fuel centerline temperature is obtained when the present correlation is combined with HALDEN thermal conductivity. On the other hand, when it is combined with SIMFUEL thermal conductivity, which does not consider the effect on thermal conductivity of fission gases and other volatile fission products, lower centerline temperature is obtained due to the characteristics of the SIMFUEL.