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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
F. W. Barclay, K. W. Dormuth
Nuclear Science and Engineering | Volume 53 | Number 4 | April 1974 | Pages 436-439
Technical Paper | doi.org/10.13182/NSE74-A23374
Articles are hosted by Taylor and Francis Online.
A system of equations is given that can be used to compute the total energy release rate, as a function of time, due to fission-product decay in a uranium-fueled reactor with a time-dependent flux. The use of the equations is demonstrated by simulating a reactor power maneuver with the time variation of fission-product power accounted for, and their time integral is compared with experimental measurements.
