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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
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.
