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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.
William G. Davey
Nuclear Science and Engineering | Volume 32 | Number 1 | April 1968 | Pages 35-45
Technical Paper | doi.org/10.13182/NSE68-A18821
Articles are hosted by Taylor and Francis Online.
The fission cross sections of 232Th, 233U, 234U, 235U, 236U, 237Np, 238U, 239Pu, 240Pu, 241Pu, and 242Pu from 1 keV to 10 MeV published up to July, 1965, were analyzed previously to select best fission cross sections for fast-reactor analysis. Since the completion of that work, new data have been produced which necessitate reevaluation of the fission cross sections particularly in the region 1 to 5 MeV. The revised data presented here are believed to be of greater consistency and, hence, accuracy than the previous selection.