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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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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Nuclear News 40 Under 40: The wait is over
Following the enthusiastic response from the nuclear community in 2024 for the inaugural NN 40 Under 40, the Nuclear News team knew we had to take up the difficult task in 2025 of turning it into an annual event—though there was plenty of uncertainty as to how the community would receive a second iteration this year. That uncertainty was unfounded, clearly, as the tight-knit nuclear community embraced the chance to celebrate its up-and-coming generation of scientists, engineers, and policy makers who are working to grow the influence of this oft-misunderstood technology.
Lorenzo P. Pagani, George E. Apostolakis
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 9-17
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3685
Articles are hosted by Taylor and Francis Online.
The work presented in this paper is part of the broader issue of quantification of safety margins within a load-capacity framework in which uncertainties in loads and capacities are identified and quantified. The present paper describes an example of quantification of uncertainty in the capacity, i.e., the fuel failure enthalpy given a burnup level. The phenomena arising at high burnup are characterized by large uncertainties, as indicated by the scatter in the experimental data. We propose a framework for the probabilistic analysis of the failure limit, i.e., the enthalpy at failure, as a function of burnup. As an example, we obtain the distribution of the failure enthalpy for a Ziracloy-4 rod subjected to a reactivity-initiated accident in a pressurized water reactor by propagating the relevant uncertainties. We use the FRAPCON and FRAPTRAN computer codes, as well as a model for the probability of spallation, to simulate the transient and to obtain data points to derive the conditional probability distribution of the failure enthalpy at a given burnup level. The final results show that the distribution of the failure enthalpy shifts to lower values as burnup increases and that spallation is an important phenomenon.