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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
G. A. Porter, M. Delgado, Y. A. Hassan
Nuclear Technology | Volume 206 | Number 4 | April 2020 | Pages 565-576
Technical Paper | doi.org/10.1080/00295450.2019.1666600
Articles are hosted by Taylor and Francis Online.
Helical coil steam generators (HCSGs) are tube and shell heat exchangers under investigation due to their future in nuclear power applications. A model of an HCSG with a transverse pitch ratio of 2.98 and changing lateral pitch ratio was created to study the pressure on the surface of the tubes under low Reynolds number flow. Pressure-sensitive paint was applied to rods of an outer bundle of the test section, and instantaneous and average pressure fields were analyzed for Reynolds numbers 4000 and 6000. A comparative study showed that the pressures along the rods had nonlinear behavior. Previous studies suggested a relationship between tube bundle characteristics and the lateral pitch ratio in heat exchanger designs. Since the transverse pitch ratio is constant, the lateral pitch ratio defines the tube bundle cross section as either staggered or inline depending on the cross-section location. Averaged pressure distributions were compared to lateral pitch ratios at respective locations. The pressure distributions along the staggered cross-section portion of the test section were found to exhibit a linear behavior across the heat exchanger body. While this study focuses on average surface pressure measurements, the differences between the same lateral pitch ratio and surface pressure show disagreement with previous studies focused on constant cross-section tube bundles. Flow phenomena within tube bundles, such as vortex shedding, are suspected to be the cause of this discrepancy but a transient analysis is necessary to determine its source.