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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Fusion Science and Technology
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.
G. W. Hollenberg, T. Kurasawa, H. Watanabe, S. E. Berk, I. J. Hastings, J. Miller, Donald E. Baker, Roger E. Bauer, Raymond J. Puigh
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1349-1354
Tritium Technology | doi.org/10.13182/FST89-A39876
Articles are hosted by Taylor and Francis Online.
An in situ tritium recovery experiment has been designed and is being fabricated for the irradiation of Li2O in the Fast Flux Test Facility, FFTF. Two in situ tritium recovery canisters will be irradiated with lithium atom burnups to 4%. One canister will provide fundamental data on tritium release as a function of temperature, gas composition, and flow rate. The other canister will contain solid pellet specimens with large (430°C) radial temperature gradients in order to provide integrated performance data.
