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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.
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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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Fusion Science and Technology
Latest News
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
S.Beloglazov, M.Nishikawa, T.Tanifuji
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1049-1053
Blanket Material and Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22744
Articles are hosted by Taylor and Francis Online.
In this paper we propose a model to explain tritium release from irradiated Li2ZrO3 sample made by Mitsubishi Atomic Power Industries Inc. (MAPI). The release curves were obtained by temperature programmed desorption (TPD) techniques in a series of experiments in Kyoto University Reactor (KUR) and in the JRR-4 reactor of the Japan Atomic Energy Research Institute (JAERI). In the model a number of mass transfer steps were taken into account. There were diffusion of tritium in the grain, adsorption and desorption of water on the surface of grains, two types of isotope exchange reactions, water formation reaction in addition of hydrogen to the purge gas. Tritium release curves for different purge gas compositions (N2, N2 + H2O) were calculated to compare with data obtained in the experiments. Apparent diffusivities of tritium in crystal grain of Li2ZrO3 were determined.
