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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Wen-Shan Lin, Chien-Hsiung Lee, Bau-Shei Pei
Nuclear Technology | Volume 88 | Number 3 | December 1989 | Pages 294-306
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34312
Articles are hosted by Taylor and Francis Online.
Based on the Helmholtz instability at the microlayer/vapor interface as a trigger condition for microlayer dryout, Lee and Mudawwar developed a mechanistic critical heat flux (CHF) model for subcooled flow boiling. An improved CHF model is implemented with more solid theoretical bases for subcooled and low-quality flow boiling under pressurized water reactor conditions. Comparisons between the predictions and experimental data show that the present model is more accurate than the well-known theoretical CHF model of Weisman and Pei and the empirical CHF correlations of W-3, Bowring, and Katto and Ohno for water flowing through uniformly heated round tubes within the applicable ranges. The applicability of the present model to rod bundles is also under investigation. Highly satisfactory results are obtained from the comparisons of predicted to observed bundle critical power.