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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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.
E. U. Khan
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 479-496
Technical Paper | Reactor | doi.org/10.13182/NT72-A31217
Articles are hosted by Taylor and Francis Online.
In order to ensure that data from vessel model flow tests are reliable, it is necessary to simulate hydrodynamically the various reactor components within the vessel, including the core. Modeling of the core is complex because, unlike other internals, a three-dimensional flow distribution must be taken into account. Core simulation criteria have been derived from the basic conservation laws governing fluid motion within the rod bundles that constitute the core. Using the criteria derived, along with any constraints imposed by the test loop, methodology for the design of a model core which hydrodynamically simulates the prototype core to a good degree of accuracy has been developed. Economic and fabrication considerations are taken into account in selecting the final design.