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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
David A. Greene
Nuclear Technology | Volume 18 | Number 3 | June 1973 | Pages 267-276
Technical Paper | Material | doi.org/10.13182/NT73-A31300
Articles are hosted by Taylor and Francis Online.
When water and sodium react, hydrogen is released to enter cover gas spaces and become absorbed into the sodium. Changes in hydrogen concentration are measured with suitable instruments to monitor steam generator vessels for water leakage. Interpreting the amplitude and rate of change of signals as potential damage to the unit requires two correlations:
and the quantity of hydrogen released by a given quantity of water is shown to be given by a model based on the equilibrium pressure of hydrogen above sodium. These correlations were developed for wastage damage and hydrogen release for a given quantity of water. Based on these correlations, system shutdown criteria were written to guide the operator of a steam generator test rig should a small water-to-sodium leak occur. Predictions from the correlations were used to specify a leak detection system for both a test facility and a plant steam generator. To meet these specifications, it is essential that the in-sodium detection of hydrogen by hydrogen diffusion tube meters become a stable and reliable technique. Operating experience with the leak detection system on the steam generator test rig test facility (which monitored naturally occurring leaks) showed that the shutdown criteria were practical and realistic in guiding system operators.