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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
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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Hubertus Nickel, Florian Schubert
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 649-660
H. Design Codes and Life Prediction | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33486
Articles are hosted by Taylor and Francis Online.
Based on the existing structural design code for pressure vessel and nuclear light water reactor power stations, situations for metallic structures in hightemperature gas-cooled reactors (HTGRs) are described for those metallic structures that mainly operate in temperature ranges of time-independent and time-dependent materials properties. The ASME Code Case N 47 is critically reviewed. For advanced HTGRs with components for operating temperatures >800°C, no nuclear accepted structural design code exists. The status of the ongoing work for the basis of those codes is given with the main emphasis on the situation in the Federal Republic of Germany.
