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Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
N. Venkataramani, F. Ghezzi, G. Bonizzoni, W. T. Shmayda
Fusion Science and Technology | Volume 29 | Number 1 | January 1996 | Pages 91-104
Technical Paper | Tritium System | doi.org/10.13182/FST96-A30659
Articles are hosted by Taylor and Francis Online.
A follow-up is done to earlier work on the conversion of isotopic waters to hydrogen isotopes, and it involves the reaction behavior of water vapor with Zr(V0.5Fe0.5)2 getter alloy under water vapor flow conditions. The efficiency of the alloy, for the conversion of H2O and D2O to H2 and D2, respectively, has been measured at different reactor pressures in the range of 10 to 330 Pa for different alloy temperatures in the range of 150 to 400°C and with hydrogen and oxygen concentrations in the alloy ≤ 250 mmol/mol of alloy. The conversion efficiency was measured to be in the range of 25 to 35% at reactor pressures of ≈250 Pa for water vapor flow rates of ≈0.3 µmol/g of alloy per second, while it was found to be in the range of 70 to 80% at reactor pressures ≤20 Pa with flow rates of ≤0.02 µmol/g of alloy per second. These experiments demonstrate the feasibility of tritiated water vapor conversion to tritium using metallic getter alloys under quasi-steady-state conditions; this feasibility is very relevant to the fusion reactor fuel cycle.