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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
Geological work begins on Poland’s first nuclear plant
Project management firm Bechtel started site geological surveys for Poland’s first nuclear power plant project, the company announced on Wednesday.
Bechtel will conduct in-depth geological surveys at the Lubiatowo-Kopalino site in the Pomeranian municipality of Choczewo, in northern Poland. This is a key milestone for the country’s entry into nuclear power production, as the surveys will inform the suitability of the planned site.
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.