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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 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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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
K. O. Ott, J. F. Marchaterre
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 179-188
Technical Paper | Nuclear Safety | doi.org/10.13182/NT81-A32663
Articles are hosted by Taylor and Francis Online.
A general methodology for the statistical evaluation of design-error related accidents is proposed that can be applied to a variety of systems that evolves during the development of large-scale technologies. The evaluation aims at an estimate of the combined “residual” frequency of yet unknown types of accidents “lurking” in a certain technological system. A special categorization of incidents and accidents is introduced to define the events that should be jointly analyzed. The resulting formalism is applied to the development of U.S. nuclear power reactor technology, considering serious accidents (category 2 events) that involved, in the accident progression, a particular design inadequacy. The analysis of the five events in that category indicates a drastic reduction (by more than a factor 50) in the combined residual frequency between the Experimental Breeder Reactor I and the Three Mile Island 2 accidents.