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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
G. V. Alm, E. E. Garrett, M. H. Binstock
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 73-82
Technical Paper | doi.org/10.13182/NSE60-A25700
Articles are hosted by Taylor and Francis Online.
The methods used for fabrication of finned aluminum-clad flat plate fuel elements are discussed. Uranium—3.5 w/o Molybdenum alloy core plates were fabricated by vacuum casting in graphite molds. The uranium alloy plate was electroplated with nickel and inserted into an extruded aluminum sheath containing external fins. Aluminum end plugs were inserted to complete the fuel plate assembly. A core-to-cladding metallurgical bond was obtained by hot gas pressing (isostatic pressing) the assembly. Bonded plates were end machined, inspected, stacked, clipped, and loaded into a stainless steel container box. Cast stainless steel end hardware was then affixed by heliarc welding to the respective box ends to result in the completed fuel element. Methods for process control are discussed. Preliminary irradiation results are presented which indicate that the elements produced by the described process are suitable for organic moderated reactor use.