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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
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Latest News
Comments on U.S. nuclear export controls on China
As trade negotiations are in the works between the United States and China, Washington, D.C., has the advantage in semiconductors but nuclear power is a different story, according to a June 9 article in the Hong Kong–based South China Morning Post.
J. H. Kittel, S. Greenberg, S. H. Paine, J. E. Draley
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 431-449
Technical Paper | doi.org/10.13182/NSE57-A25408
Articles are hosted by Taylor and Francis Online.
Three corrosion-resistant uranium-base alloys, U-3 weight per cent Nb, U-5 weight per cent Zr-1½ weight per cent Nb, and U-3.8 weight per cent Si (U3Si) were irradiated to burnups of 0.1 atomic per cent or less. Observations were made of irradiation-induced length changes in specimens of the alloys as influenced by the method of fabrication and heat treatment, and of changes in aqueous corrosion resistance resulting from irradiation. It was found that the uranium-niobium alloy was unsuitable from the standpoint of dimensional and surface stability, and its corrosion resistance was destroyed by irradiation. The uranium-zirconium-niobium alloy could be nominally stabilized under irradiation and its corrosion resistance was destroyed by between 0.046 and 0.074 atomic per cent burnup. The uranium-silicon alloy was relatively stable under irradiation and showed no increase in corrosion rate at 290°C after 0.090 atomic per cent burnup, although cracking occurred after several days corrosion testing.