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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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July 2025
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Latest News
Report: New York state adding 1 GW of nuclear to fleet
New York Gov. Kathy Hochul has instructed the state’s public electric utility to add at least 1 gigawatt of new nuclear by building a large-scale nuclear plant or a collection of smaller modular reactors, according to the Wall Street Journal.
Chongchong Tang, Martin Steinbrueck, Mirco Grosse, Sven Ulrich, Michael Stueber, Hans Juergen Seifert (KIT)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 694-700
Alumina-forming MAX phase ternary carbides are being considered as protective coatings on zirconium alloys as accident tolerant fuel (ATF) cladding because of their resistivity against high-temperature steam oxidation during accident scenarios. This study attempted to synthesize three types of Al-containing MAX phase carbides (Ti?AlC, Cr?AlC and Zr?AlC) as coatings on Zircaloy-4 substrates via deposition of elemental nanoscale multilayer thin films using magnetron sputtering, and subsequent thermal annealing in argon. Formation of Ti?AlC and Cr?AlC MAX phases was confirmed after annealing at 800°C and 550°C, respectively, while growth of Zr(Al)C carbide rather than Zr?AlC MAX phase was observed in the Zr-C-Al system. Oxidation of the three coated samples at 1000°C in steam for 1 hour revealed no protective effect of the Ti?AlC and Zr(Al)C coatings with significant spallation and cracking. The Cr?AlC coatings possess superior oxidation resistance and self-healing capability with a thin and dense ?-Al?O? layer growth on the surface, which shows good promise as a candidate for coated ATF claddings.