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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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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.
Philip J. Ennis, Klaus P. Mohr, Hans Schuster
Nuclear Technology | Volume 66 | Number 2 | August 1984 | Pages 363-368
C.4. Short-Term Property | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33439
Articles are hosted by Taylor and Francis Online.
Carburization of high-temperature alloys has been frequently observed during exposure to dry high-temperature gas-cooled reactor (HTGR) helium compositions. Therefore, the influence of carburization on mechanical properties of alloys that may be used for HTGR high-temperature components has been studied. In creep rupture tests on high-temperature alloys for up to 20 000 h, the data in air and in various simulated HTGR heliums lie in the same scatterband irrespective of carburization that has been observed in the contaminated helium atmospheres. The dependence of room temperature tensile properties and the impact strength in the 20 to 800 °C range on the carburization level has been measured so that the maximum carbon level for a given room temperature ductility and impact strength could be specified. The results showed that the minimum room temperature elongation fell to below 5% when the carbon content exceeded 0.5 wt% for Incoloy-800H and 0.2 wt% for lnconel-617. At these carbon levels, the alloys have impact strengths (ISO V-notch specimens) of ∼50 J or above at temperatures in the 25 to 800°C range.