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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.
Meeting Spotlight
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
Latest News
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.
D. R. Novog, S. T. Yin, J. S. Chang
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 880-884
Technical Paper | First Wall, Blanket, and Shield | doi.org/10.13182/FST07-A1604
Articles are hosted by Taylor and Francis Online.
This paper presents the results of an experimental investigation conducted for high heat flux subcooled boiling heat transfer and pressure drop in a tubular channel under both smooth- and swirl-flow of high velocity water. High heat flux flow boiling is of interest to Fusion reactor first wall cooling. Test conditions covered a mass flux range from 5 to 10 Mg/m2 s, inlet temperatures from 100 to 175°C and system pressures from 2.0 to 5.0 MPa. The maximum heat flux tested was 12 MW/m2. The test section diameter used in this study was 5.30 mm (I.D.) with an axial heated length of 356 mm. To ensure accurate results, a significant number of heat balance tests were performed with a minimum and maximum heat balance error of 1.5%. Swirl-flow tests were performed using twisted tape inserts with thickness 0.8 mm with twist ratios between 2 and 4. To measure heat transfer performance, 15 miniature thermocouples were used to measure the tube outside wall temperature at various axial and circumferential positions. Differential pressure transducers were used to measure the axial pressure drop at several locations along the test section under single- and two-phase conditions.