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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
R.H. Jones, C.H. Henager, Jr., G.E. Youngblood, H.L. Heinisch
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 969-976
Fusion Materials | doi.org/10.13182/FST96-A11963062
Articles are hosted by Taylor and Francis Online.
Silicon carbide composites are attractive for structural applications in fusion energy systems because of their low activation and afterheat properties, excellent high-temperature properties, corrosion resistance and low density. Another attractive property includes the potential to engineer their properties by location within a component or system to meet variable performance requirements. This can be accomplished by tailoring the fiber type, volume fraction and architecture by location within the component. Also β SiC exhibits very low swelling (< 0.2%) over the temperature range of 800 to 1000°C.
These composites are relatively new materials with a limited data base; however, there is sufficient understanding of their performance to identify key issues in their application. These issues include: mechanical, chemical and radiation stability, nuclear transmutation, hermetic behavior, thermal conductivity, mechanical and thermal fatigue, thermal shock, joining and design methodology. Progress is being made on several of these issues in the U.S., European Union and Japanese fusion materials programs and through collaborations between these programs.