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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.
B. Rouben, K. S. Brunner, D. A. Jenkins
Nuclear Science and Engineering | Volume 98 | Number 2 | February 1988 | Pages 139-148
Technical Paper | doi.org/10.13182/NSE88-A28493
Articles are hosted by Taylor and Francis Online.
A refinement is proposed to the current method of evaluating lattice properties for use in calculations of Canada deuterium uranium flux distributions. This refinement, labeled the local-parameter calculation, takes into account locally appropriate values of coolant density, fuel temperature, and flux/power level where core average values were previously used. The local-parameter calculation has been implemented and tested. Results are compared to those of previous calculations and of independent methods based on in-core measurements.
