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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
Si Y. Lee, L. Larry Hamm, Frank G. Smith III
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 254-263
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-86
Articles are hosted by Taylor and Francis Online.
It has been proposed to build an accelerator for the production of tritium. A transient natural convection model of the accelerator blanket primary heat removal (HR) system was developed to demonstrate that the blanket could be cooled for a sufficient period of time for long-term cooling to be established following a loss-of-flow accident (LOFA). The particular case of interest in this work is a complete LOFA. For the accident scenario in which pumps are lost in both the target and blanket HR systems, natural convection provides effective cooling of the blanket for ∼68 h, and if only the blanket HR systems are involved, natural convection is effective for ∼210 h. The heat sink for both of these accident scenarios is the assumed stagnant fluid and metal on the secondary sides of the heat exchangers.