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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
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
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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.
F. N. Mazandarany, G. Y. Lai
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 349-365
Technical Paper | Material | doi.org/10.13182/NT79-A19223
Articles are hosted by Taylor and Francis Online.
Corrosion of carbon steel, Cr—1 Mo, Types 422, 304, and 316 stainless steel, Alloy 800 (Grade 2), Alloy 800 H, Inconel 617, and Hastelloy X by gaseous impurities in a simulated steam-cycle high-temperature gas-cooled reactor helium environment was investigated. The corrosion tests were conducted at various temperatures for up to 5000 h. Oxidation was observed in all the alloys investigated except carbon steel as predicted by thermodynamic calculations. Other gas-metal reactions observed included carbon deposition on carbon steel and Cr—1 Mo, and carburization in Type 316 stainless steel with the as-received surface condition (i.e., annealed and pickled). Thermodynamic considerations were given to rationalize the chemical reaction(s) that dominates the carbon potential in the test environment and to provide a basis for making thermodynamic predictions as to the occurrence of carbon deposition, carburization, and/or decarburization.