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Fusion energy: Progress, partnerships, and the path to deployment
Over the past decade, fusion energy has moved decisively from scientific aspiration toward a credible pathway to a new energy technology. Thanks to long-term federal support, we have significantly advanced our fundamental understanding of plasma physics—the behavior of the superheated gases at the heart of fusion devices. This knowledge will enable the creation and control of fusion fuel under conditions required for future power plants. Our progress is exemplified by breakthroughs at the National Ignition Facility and the Joint European Torus.
P.A. Finn, R.G. Clemmer, L. Greenwood, A. Lide, D.K. Sze, J.L. Anderson, R. Sherman, J.R. Bartlit, Y. Naruse, H. Yoshida
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 680-686
Blanket and Shield Design | doi.org/10.13182/FST89-A39776
Articles are hosted by Taylor and Francis Online.
A breeder blanket interface for an aqueous lithium salt blanket is defined for TSTA. High calculated radiolysis rates result in a high overpressure in the blanket and the need for a depressurizer and a recombiner system. High projected corrosion rates for stainless steel and for beryllium result in high activity levels in the blanket and the possible dissolution of the beryllium balls. The required tritium processing systems are complex, involving seven separation steps. A flow sheet is presented of the needed tritium systems. The main processing units to recover tritium from the salt solution are a flash evaporator with condenser, a water distillation unit, and a vapor phase chemical exchange (VPCE) unit. The gas product stream from the blanket has an H/T ratio of 105 which requires a dedicated cryodistillation unit of very high capacity. This unit has a first column with a diameter of almost one meter to decrease the H/T ratio to 10.