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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Latest News
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.
Peter Schreiber, Pavol Tanuska, Robert Vrabel, Pavel Vazan
Nuclear Technology | Volume 185 | Number 2 | February 2014 | Pages 208-215
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-138
Articles are hosted by Taylor and Francis Online.
In this paper, we develop a new method for determining the residual power of used nuclear fuel (UNF). The method is based on the heat transfer analysis of UNF in a C-30 transport container with a KZ-48 compact storage cask. We compare the results achieved by the currently used SCALE 6 software packages based on nuclear physics calculations and the results from our method.