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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
N. Kaffezakis, D. Kotlyar
Nuclear Technology | Volume 206 | Number 1 | January 2020 | Pages 48-72
Technical Paper | doi.org/10.1080/00295450.2019.1616475
Articles are hosted by Taylor and Francis Online.
This paper details the development and optimization of a novel seed blanket fuel assembly designed for utilizing high-conversion Th-233U fuel cycles in the current fleet of pressurized water reactor vessels. Previous studies have revealed the necessity to downrate the total power of cores loaded with seed blanket assemblies due to issues with high power density in the seed regions and thermal-hydraulic failure. This new design features solid packing of the blanket region with the objective of increasing the total power and the economic competitiveness. This paper utilized the Serpent code to study the depletion of various designs of the solid blanket assembly, and THERMO is utilized for thermal-hydraulic analysis. A favorable design was developed that attained an excess 1.7% fissile material from the initial loading and that can be run at a maximum power up to 66% greater than the comparable designs used as references in this paper.
