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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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NN Asks: What did you learn from ANS’s Nuclear 101?
Mike Harkin
When ANS first announced its new Nuclear 101 certificate course, I was excited. This felt like a course tailor-made for me, a transplant into the commercial nuclear world. I enrolled for the inaugural session held in November 2024, knowing it was going to be hard (this is nuclear power, of course)—but I had been working on ramping up my knowledge base for the past year, through both my employer and at a local college.
The course was a fast-and-furious roller-coaster ride through all the key components of the nuclear power industry, in one highly challenging week. In fact, the challenges the students experienced caught even the instructors by surprise. Thankfully, the shared intellectual stretch we students all felt helped us band together to push through to the end.
We were all impressed with the quality of the instructors, who are some of the top experts in the field. We appreciated not only their knowledge base but their support whenever someone struggled to understand a concept.
Michael Avery, Jun Yang, Mark Anderson, Michael Corradini, Earl Feldman, Floyd Dunn, James Matos
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 249-258
Technical Paper | doi.org/10.13182/NSE11-69
Articles are hosted by Taylor and Francis Online.
An experimental study of low-pressure, natural convection critical heat flux (CHF) has been carried out with full-scale fuel pins, simulating typical Training, Research, Isotopes, and General Atomics (TRIGA) reactor conditions. The test section is an annular upwardly flowing channel formed by a round tube and a simulated fuel pin heater rod with a chopped-cosine power profile, located in the center of the tube. Experiments were performed under the following conditions: inlet water subcooling varying from 10 to 70 K, pressure varying from 110 to 200 kPa, and natural circulation mass flux up to 400 kg/m2s. CHF was observed, and associated data have been compared with selected CHF correlations. It has been found that the CHF increases as the pressure or mass flux increases, but does not significantly depend on the inlet subcooling. Among the numerous presented CHF data and correlations, few data exist, and no specific correlations have been developed for TRIGA reactor conditions. Because of the lack of specific correlation, the correlations of Bernath, El-Genk et al., Mishima and Ishii, and Block and Wallis have been used to estimate the TRIGA CHF outside of their intended ranges of applicability. These correlations are evaluated against the current experimental data.
