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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
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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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
Michal Cihlář, Pavel Zácha, Jan Uhlíř, Martin Mareček, Václav Dostál, Jan Prehradný
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 2961-2976
YMSR Paper | doi.org/10.1080/00295639.2023.2189549
Articles are hosted by Taylor and Francis Online.
The Experimental Molten FLiBe Salt Loop (MSL), which was previously damaged during operation, is currently undergoing renovation using a risk-based design approach. An important part of this approach is to reliably define and explore normal and abnormal states of the MSL in order to avoid repeating such failures. A numerical model consisting of heated walls and working fluid volume was created for the ANSYS Fluent code. The quality of this model was checked, and sensitivity analysis for mesh quality was performed. Moreover, another sensitivity analysis was performed for the heat transfer coefficient between the insulation and the surrounding air. A number of different normal and abnormal states were identified, investigated, and described, including the loop filling process, regular operation with natural circulation or forced circulation, heating cutoff without draining, and insulation failure. The results of these investigations will be used for the risk-based design of the MSL renovation; for precise establishment of operation and safety limits, conditions, rules, and procedures before the MSL commissioning; and consequently, on a regular basis, for the risk-based operation, experiments, and maintenance of the MSL.