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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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ANS names 2026 Congressional Fellows
Kasper
Hayes
The American Nuclear Society has officially selected two of its members to serve as its 2026 Glenn T. Seaborg Congressional Science and Engineering Fellows. Alyssa Hayes and Benjamin Kasper will help the Society fulfill its strategic goal of enhancing nuclear policy by working in the halls of Congress, either in a congressional member’s personal office or with a committee, starting next January.
“The Congressional Fellowship program has put ANS in a unique position to provide significant technical assistance to Congress on nuclear science, energy, and technology, with great results,” said Congressional Fellowship Special Committee chair Harsh Desai, himself a former Congressional Fellow. “This once-in-a-lifetime professional development opportunity will allow them to learn the art of policymaking and potentially pursue it as part of their careers beyond the fellowship.”
Abdellatif M. Yacout, Stefano Salvatores, Yuri Orechwa
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 177-189
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35187
Articles are hosted by Taylor and Francis Online.
Failure times of components are traditionally used to evaluate their reliability. An alternate approach is to analyze the degradation data accumulated during the component’s testing or during its normal operation. Degradation analysis is particularly useful when it is not possible to observe a significant number of failures. This is the case for metallic Integral Fast Reactor fuel pins irradiated in Experimental Breeder Reactor II, where failures have not taken place under normal operating conditions. A degradation analysis methodology is presented and applied to these pins. The time-to-failure distribution for the fuel pins is estimated based on a fixed threshold failure model. The confidence intervals of the distribution are calculated using a parametric bootstrap method.