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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
Arkadiy A. Yukhimchuk, Vladimyr A. Arkhangel'sky
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 826-830
Design and Model | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22700
Articles are hosted by Taylor and Francis Online.
This paper presents a schematic design of Tritium Fuel Cycle for Muon-Catalyzed Intense Neutron Source (MC INS) capable of producing monochromatic 14 MeV neutrons. Based on the assumption that the fuel mixture should be used in a liquid phase the different approaches are proposed to incorporate a DT cell (synthesizer) into the MC INS facility The estimations of total tritium inventory in ihe MC INS facility are given. The calculations of the DT cell operation temperature regime using the code FLOW 3D are presented. It is shown the capability to remove the thermal energy released in the DT cell of the proposed design. The MC INS design is analyzed from the viewpoint of tritium safety requirements.