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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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The current status of heat pipe R&D
Idaho National Laboratory under the Department of Energy–sponsored Microreactor Program recently conducted a comprehensive phenomena identification and ranking table (PIRT) exercise aimed at advancing heat pipe technology for microreactor applications.
B. W. LeTourneau, R. E. Grimble
Nuclear Science and Engineering | Volume 1 | Number 5 | October 1956 | Pages 359-369
Technical Paper | doi.org/10.13182/NSE56-A28774
Articles are hosted by Taylor and Francis Online.
In the thermal design of nuclear power reactors having parallel coolant channels, engineering hot channel factors have been established to account for small dimensional deviations from the nominal design of the reactor fuel elements resulting from manufacturing tolerances, and for departures from ideal flow conditions. A description of the various deviations from nominal likely to be encountered in a practical reactor design is presented, together with methods for estimating the magnitude of the effect of each on channel enthalpy rise, film temperature difference, and maximum heat flux. Examples are given for a geometry consisting of parallel plate type fuel elements separated by rectangular coolant channels.