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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.
W. Chubb, A. C. Hott, B. M. Argall, G. R. Kilp
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 486-495
Technical Paper | Material | doi.org/10.13182/NT75-A24449
Articles are hosted by Taylor and Francis Online.
Early in 1972, confirmation was obtained that gaps observed in the columns of fuel pellets in the cores of several pressurized water reactors were the result of densification of the fuel during operation. The implications of these gaps with regard to fuel rod integrity and reactor safety stimulated a substantial effort to understand in-pile densification at low temperatures and to provide corrective action. Data obtained in the course of irradiation and by postirradiation examinations have disclosed that in-pile densification is controlled by the microstructure of the fuel, particularly its pore size distribution and porosity. These factors, in turn, were found to be controlled by fabrication parameters of which the sintering conditions were most important. The background, data, and theory of densification are reviewed. As a consequence, appropriate controls have been placed on fuel density, microstructure, and sintering conditions to reduce in-pile densification to insignificant levels.