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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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.
William G. Davey
Nuclear Science and Engineering | Volume 19 | Number 3 | July 1964 | Pages 259-273
Technical Paper | doi.org/10.13182/NSE64-A20960
Articles are hosted by Taylor and Francis Online.
Over fifty fast critical assemblies have been studied in the Zero Power Reactor - III (ZPR-III) of Argonne National Laboratory since it started operation in 1955. All of these assemblies were fueled with U235 and reflected with depleted uranium; the core volumes ranged from 2 to 660 liters and the critical masses ranged from 26 to 580 kg of U235. The experimental characteristics of a representative group of 23 of these assemblies in which oxide, carbide and metallic fuels were simulated have been compared with calculated values. The parameters studied were critical size, central fission ratios, prompt-neutron lifetimes and the reactivity effects of substitution of various materials at the reactor center.