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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Kevin J. Chan, Preet M. Singh
Nuclear Technology | Volume 206 | Number 11 | November 2020 | Pages 1751-1768
Technical Paper | doi.org/10.1080/00295450.2020.1809311
Articles are hosted by Taylor and Francis Online.
Austenitic alloys such as austenitic stainless steels and Ni-based alloys have been specified as container materials for molten salt reactors (MSRs). In MSR environments, these alloys are susceptible to carburization because (1) graphite components provide a source of carbon, (2) oxide films are not protective in molten halide salts, and (3) MSR operating temperatures fall within the temperature range of carbide formation. Carburization may occur simultaneously with corrosion by the selective dissolution of Cr. To study the corrosion behavior of a carburized microstructure, Hastelloy N, Haynes 244, Haynes 230, and Incoloy 800H samples were pre-carburized at 900°C in a hydrocarbon atmosphere prior to exposure to molten FLiNaK at 700°C. Pre-carburized samples featured a carbide-rich microstructure, particularly near the sample surface. The face-centered-cubic matrix of pre-carburized samples was found to be depleted in Cr, Mo, and to a lesser extent W, which are strong carbide-forming elements. Chromium dissolution in pre-carburized samples was suppressed compared to untreated samples due to the reduction in Cr activity. However, selective attack of the connected carbide structure along grain boundaries was observed in pre-carburized Haynes 230 and Incoloy 800H, which are alloys with high Cr content.