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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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
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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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The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Robert Petroski, Benoit Forget, Charles Forsberg
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 28-45
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14517
Articles are hosted by Taylor and Francis Online.
A fuel cycle option is evaluated in which fuel bred in breed-and-burn (B&B) reactors is used to start up additional B&B reactors, with the fuel being recycled using limited-separations processes instead of full actinide reprocessing. This fuel cycle aims to minimize processing requirements and proliferation risk while still being able to achieve exponential growth and high uranium utilization. The neutron excess concept is applied to compute the starting fuel requirements of new B&B reactors, allowing fleet doubling times to be estimated. A simple analytic expression for doubling time is derived, which is applied to example B&B reactors using a hypothetical core composition. It is found that larger reactors are able to achieve shorter doubling times because of their smaller starter fuel requirements per unit power. Several variant fuel cycle configurations are examined, and their doubling times are computed.