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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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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
A. Perevezentsev, J. Hemmerich
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 797-800
Hydride and Storage | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22694
Articles are hosted by Taylor and Francis Online.
Storage of tritium in the form of metal hydride is a common technique in tritium handling facilities and is generally acknowledged as the only option for the storage of large tritium inventories in future fusion reactor applications. Since accounting for large inventories by the conventional TPVC (Temperature, Pressure, Volume, Concentration) is very cumbersome, it is highly desirable to perform accounting directly by the application of calorimetric methods, for example based on monitoring of temperature rise in the tritium storage container caused by heat of the tritium decay (1.95W/mol.T2). Following an earlier evaluation1 of the JET tritium storage containers by electrical simulation of heat of the tritium decay the viability of the method was proven by adiabatic calorimetry with known tritium inventories up to ≈5900TBq.
