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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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
M. M. R. Williams, J. M. Kallfelz
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 416-419
Technical Note | doi.org/10.13182/NSE78-A27170
Articles are hosted by Taylor and Francis Online.
An analysis is made of the accuracy of the buckling approximation for the transverse leakage, used in various one- and two-dimensional transport theory computer codes. We find that the resulting approximate integro-differential form of the transport equation is not suitable for calculating accurate values of the angle-dependent flux for any case where transverse leakage has an appreciable effect on the solution. We have taken four problems, namely, critical equation, pulsed neutron and diffusion length problems, and extrapolated endpoints, and have solved them exactly using an equation derived in an earlier paper; we then solve the same problem by means of the buckling equation. In all cases, important deviations are noted that restrict the use of the buckling approximation.