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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.
David A. Greene
Nuclear Technology | Volume 18 | Number 3 | June 1973 | Pages 267-276
Technical Paper | Material | doi.org/10.13182/NT73-A31300
Articles are hosted by Taylor and Francis Online.
When water and sodium react, hydrogen is released to enter cover gas spaces and become absorbed into the sodium. Changes in hydrogen concentration are measured with suitable instruments to monitor steam generator vessels for water leakage. Interpreting the amplitude and rate of change of signals as potential damage to the unit requires two correlations:
and the quantity of hydrogen released by a given quantity of water is shown to be given by a model based on the equilibrium pressure of hydrogen above sodium. These correlations were developed for wastage damage and hydrogen release for a given quantity of water. Based on these correlations, system shutdown criteria were written to guide the operator of a steam generator test rig should a small water-to-sodium leak occur. Predictions from the correlations were used to specify a leak detection system for both a test facility and a plant steam generator. To meet these specifications, it is essential that the in-sodium detection of hydrogen by hydrogen diffusion tube meters become a stable and reliable technique. Operating experience with the leak detection system on the steam generator test rig test facility (which monitored naturally occurring leaks) showed that the shutdown criteria were practical and realistic in guiding system operators.