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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
What’s the most difficult question you’ve been asked as a maintenance instructor?
Blye Widmar
"Where are the prints?!"
This was the final question in an onslaught of verbal feedback, comments, and critiques I received from my students back in 2019. I had two years of instructor experience and was teaching a class that had been meticulously rehearsed in preparation for an accreditation visit. I knew the training material well and transferred that knowledge effectively enough for all the students to pass the class. As we wrapped up, I asked the students how they felt about my first big system-level class, and they did not hold back.
“Why was the exam from memory when we don’t work from memory in the plant?” “Why didn’t we refer to the vendor documents?” “Why didn’t we practice more on the mock-up?” And so on.
Thomas D. Radcliff, William S. Johnson, J. Roger Parsons, Douglas E. Ekeroth
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 100-109
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34952
Articles are hosted by Taylor and Francis Online.
Formation of vortices in the lower plenum of existing nuclear power reactors has been hypothesized to cause observed localized coolant starvation, which results in a loss of thermal margin. A 1:9 scale model was built to study vortex formation and suppression in the Westinghouse AP600 advanced reactor design. Geometric similarity was maintained in the regions upstream of the reactor core. Air was used as the working fluid, and a wide range of model velocities were tested. Flow fields in the plenum were visualized with smoke injection and a tuft grid. Twin counterrotating vortices were observed. It is thought that these vortices were induced by viscous shear. The vortices were tested for sensitivity to overall reactor flow, imbalances in the individual coolant loop flows, and position of alignment keyways. Suppression of these vortices was achieved with a passive device placed in the lower plenum. The effect of this device at different axial elevations was studied.