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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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
K. Nishina, A. Z. Akcasu
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 170-181
Technical Paper | doi.org/10.13182/NSE70-A21197
Articles are hosted by Taylor and Francis Online.
Energy-dependent diffusion theory with a modified one-term degenerate kernel is employed to derive an expression for the detector response in neutron-wave experiments performed in a slab and a cylinder of crystalline moderator. The Watson transform and the Laplace transform modified to finite systems are used and different mathematical representations of the detector output are discussed. From the derived expressions, various decaying modes, including the continuum mode, are calculated for a 100-cm graphite slab. The condition for the existence of the discrete mode is studied, and the maximum frequencies obtained are 7440 cps for graphite and 9300 cps for beryllium. The experiment reported by Utsuro et al. is interpreted and the observed interference pattern is reproduced analytically with a slight discrepancy in the resonance frequency. The potential of this experiment for measuring moderator properties is also discussed.
