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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.
Bruce E. Schmitt
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 26-29
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33660
Articles are hosted by Taylor and Francis Online.
The computer code RETRAN-02 is being used to analyze operational transients at the Hanford N Reactor. Included in the scope of the transients is a loss of feedwater from two 430-MW(electric) turbines to the secondary cooling system. An actual loss of feedwater from one of the two turbines occurred prior to this analysis, and plant data obtained from this transient were used in the validation of the RETRAN computer model. These data are compared with the RETRAN-02 predictions.
