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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
October 2025
Latest News
Atomic Canyon partners with INL on AI benchmarks
As interest and investment grows around AI applications in nuclear power plants, there remains a gap in standardized benchmarks that can quantitatively compare and measure the quality and reliability of new products.
Nuclear-tailored AI developer Atomic Canyon is moving to fill that gap by entering into a new strategic partnership with Idaho National Laboratory to develop and release the “first comprehensive benchmark suite for evaluating retrieval-augmented generation (RAG) and large language models (LLMs) in nuclear applications.”
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.
