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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
T. Kurasawa, R. A. Verrali, O. D. Slagle, G. W. Hollenberg
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 931-937
Blanket Technology | doi.org/10.13182/FST91-A29463
Articles are hosted by Taylor and Francis Online.
The BEATRIX-II experiment in FFTF is an in-situ tritium recovery experiment to evaluate the tritium release characteristics of Li2O and its stability under fast neutron irradiation to extended burnups. This experiment includes two specimens: a thin annular ring specimen capable of temperature transients and a solid temperature gradient specimen. During the first 85 days of the operating cycle of the reactor, the tritium recovery rate of a temperature transient capsule was examined as a function of temperature, gas flow rate, gas composition and burnup. Temperature changes in the range from 500 to 650°C resulted in decreasing tritium inventory with increasing temperature. Lower gas flow rates resulted in slightly lower tritium recovery rates while gas composition changes affected the tritium recovery rate significantly more than either flow rate or temperature changes. Three different sweep gases were used: He-0.1% H2, He-0.01% H2, and pure He. Decreasing the amount of hydrogen in the sweep gas decreased the steady-state recovery rate by as much as a factor of two. A temperature gradient capsule is more prototypic of the conditions expected in a fusion blanket and was designed to provide data that can be used in evaluating the operational parameters of a solid breeder in a blanket environment. The operation of this canister during the first 85 EFPD cycle suggests that Li2O is a viable solid breeder material.
