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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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August 2024
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Advanced nuclear workshop brings together Japanese and American experts
Tohoku University in Sendai, Japan, was the site of an advanced nuclear reactor workshop in late May that was hosted by the Fastest Path to Zero Initiative of the University of Michigan and Tohoku’s Center for Fundamental Research on Nuclear Decommissioning. The event was co-organized by the U.S. Consulate in Sapporo, Japan, and the Atlantic Council, which is associated with the North Atlantic Treaty Organization. The workshop, “The Potential Contribution of Advanced Nuclear Energy Technologies to the Decarbonization and Economic Development of Japan and the U.S.,” featured numerous American and Japanese academic authorities, government policymakers, executives of utilities and advanced reactor developers, and leaders of nongovernmental organizations. Also participating were students from both the University of Michigan and Tohoku University.
G. P. Marino
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 93-98
Technical Paper | doi.org/10.13182/NSE72-A22530
Articles are hosted by Taylor and Francis Online.
An analytical method is described which enables one to calculate the concentration profile of an interstitial solute of finite solubility in an alloy under a given thermal gradient. The method requires that one know beforehand the diffusion coefficient, the terminal solid solubility, and the heat of transport of the solute. The work is applied to the experimental conditions of Sawatzky and of Markowitz for hydrogen in Zircaloy. The agreement between the predicted profiles and the experimentally determined profiles is quite good for total concentrations less than ∼1000 ppm. For concentrations greater than this, some deviation is seen but the overall agreement is still considered good within the accuracy of the assumptions employed. The principles embodied in the analysis are easily generalized to include multidimensional thermal and concentration gradients.