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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
L. W. Ward
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 247-253
Technical Paper | Reactor | doi.org/10.13182/NT75-A24426
Articles are hosted by Taylor and Francis Online.
The behavior of the primary system coolant in a pressurized water reactor during a small-break loss-of-coolant accident (LOCA) is governed by the hydrostatic forces that develop in the system. Digital simulation of the hydrostatic interactions during a small-break LOCA can be achieved with simplified nodal representations that significantly reduce computer times. The simplification process can be successfully achieved by combining primary system regions that behave symmetrically while preserving the basic manometer or U-tube design of the system. The simplified nodal representations have the capability of assessing the hydrostatic effects on the blowdown for the spectrum of small breaks wherein detailed model computations become economically prohibitive for parametric analyses of emergency core cooling systems.