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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
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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
Shigeo Yoshida, Isao Murala, Akito Takahashi
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 432-436
Biology | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22626
Articles are hosted by Taylor and Francis Online.
Handling of a large amount of tritium and tritiated contaminants had been carried out many times repeatedly in the OKTAVIAN facility which is an accelerator of Cockcroft Walton type to produce 14 MeV fast neutrons by D-T reaction. To estimate the dose due to internal exposure following intake of tritium, the distribution of tritium concentration has been measured with the bioassay method and the liquid scintillation counting method by using bioassay samples in man such as urine, exhaled water and so on. On the basis of their many tritium concentration data accumulated in the OKTAVIAN facility until now, a new tritium metabolic model has been developed by modifying a conventional three-compartment model known as the most famous model. The present model was verified using measured data, and compared with other models proposed previously.