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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Fusion Science and Technology
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Ronald D. Boyd, Sr.
Fusion Science and Technology | Volume 18 | Number 2 | September 1990 | Pages 317-324
Technical Paper | Blanket Engineering | doi.org/10.13182/FST90-A29303
Articles are hosted by Taylor and Francis Online.
Steady-State subcooled water flow boiling experiments were carried out in a uniformly heated horizontal circular channel with a 0.45-MPa exit pressure and with the mass velocity varying from 1.56 to 8.55 Mg/m2·s. Measurements of critical heat flux (CHF), local heat transfer, and pressure drop were made for a smooth-wall 1.02-cm-diam copper test section with a heated length-to-diameter (L/D) ratio of 49.0. For the same inlet temperature near 20.0°C, comparisons are made with previous data with L/D = 33.0, from 30.0 to 50.0, 96.6 (two cases), and 115.5. The exit pressures for the above data are 0.1, 0.45, 0.77, 1.59, and 1.67 MPa, respectively. When L/D is between 49.0 and 115.5, the L/D influence on CHF is found to be significant for a 1.02-cm channel diameter in subcooled flows for mass velocities above 4.0 Mg/m2·s. This finding is important since most researchers and designers assume minimal L/D influence when L/D is >30. Further, the present CHF and local heat transfer data extend the data base (CHF near 1000.0 W/cm2 and heat transfer coefficient near 70 000 W/m2·K) for large channel diameters near 1.0 cm and low exit pressures. These results will assist in preventing catastrophic conditions from occurring in future systems where the L/D influence might inappropriately be neglected. Finally, Gambill's correlation predicts CHF significantly above the present data for CHF below 500 W/cm2. Above 500 W/cm2, however, his correlation agreed well with both the present data and the data for L/D = 96.6.