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The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Fusion Science and Technology
Latest News
Strontium: Supply-and-demand success for the DOE’s Isotope Program
The Department of Energy’s Isotope Program (DOE IP) announced last week that it would end its “active standby” capability for strontium-82 production about two decades after beginning production of the isotope for cardiac diagnostic imaging. The DOE IP is celebrating commercialization of the Sr-82 supply chain as “a success story for both industry and the DOE IP.” Now that the Sr-82 market is commercially viable, the DOE IP and its National Isotope Development Center can “reassign those dedicated radioisotope production capacities to other mission needs”—including Sr-89.
Francesco Ghezzi, Natesan Venkataramani, Andrea Conte, Giovanni Bonizzoni, W. T. Shmayda
Fusion Science and Technology | Volume 27 | Number 4 | July 1995 | Pages 458-475
Technical Paper | Tritium System | doi.org/10.13182/FST95-A30364
Articles are hosted by Taylor and Francis Online.
Experimental investigation of the reaction of light and heavy water vapors with a metallic alloy and the release of hydrogen by batch-mode conversion with a Zr(V0.5Fe0.5)2 getter is presented. The dependence of cracking of water vapor on the alloy temperature and water vapor pressure is studied. The roles of initial as well as increasing concentrations of hydrogen and oxygen in the alloy are delineated. The conversion rate constant is observed to shift from being surface dissociation process-dependent to bulk diffusion process-dominated during the conversion process. Hydrogen sorption in the alloy and its release during the batch conversion of water vapor, which assumes considerable significance from the perspective of recovering tritium as fuel gas from tritiated water waste, are discussed based on the studies performed that maintained the getter at various temperatures in the range of 100 to 400°C and over a water vapor pressure range of 50 to 500 Pa, with various hydrogen and oxygen concentrations in the getter alloy.