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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
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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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
Zhipeng Feng, Fenggang Zang, Shuai Liu, Huanhuan Qi, Xuan Huang
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 428-442
Technical Paper | doi.org/10.1080/00295639.2022.2118478
Articles are hosted by Taylor and Francis Online.
To further investigate fluid-structure–interaction problems that occur in the nuclear field such as the behavior of pressurized water reactor fuel rods, steam generator tubes, and other heat exchanger tubes, the flow-induced vibrations of two flexible tubes in tandem, side-by-side, and in staggered arrangements are investigated. First, a three-dimensional numerical model for fluid-structure interaction of flexible tubes in cross flow is developed. It is a three-dimensional fully coupled approach with solving the fluid flow and the structure vibration simultaneously. Second, results are presented in the form of force coefficients, dynamic response, trajectories, and wake vortex pattern. The effects of pitch ratio, tube arrangement, and flow velocity on the vibration response and the flow field characteristic are investigated. Critical pitch and critical velocity are obtained successfully. The critical velocity depends heavily on pitch ratio. Under the same pitch ratio and velocity, the side-by-side tubes have the maximum value of fluid force and vibration amplitude, followed by the staggered tubes the and tandem tubes in sequence. The trajectory and wake vortex pattern are highly dependent on tube arrangement, pitch ratio, and flow velocity.