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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Vistra’s Perry nuclear plant approved for license renewal
Texas-based Vistra Corporation has announced that its license renewal application for the Perry nuclear power plant was approved by the Nuclear Regulatory Commission. The plant first connected to the grid in 1986 and is still operating under its original 40-year license, which was set to expire next year.
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.