Abstract

Liquid lithium is a leading candidate as a tritium-breeding material for fusion reactors because of its good breeding and heat-transfer characteristics. The self-cooled blanket concept is particularly attractive because of the inherent simplicity associated with the use of lithium as both breeder and coolant. In addition to liquid metal magnetohydrodynamic issues (LMMHD), two major compatibility concerns arising from the use of lithium are corrosion/mass transfer and degradation of mechanical properties of the containment material. This paper describes a new experimental facility for investigating the corrosion/mass transfer/deposition mechanisms at characteristic velocities and system temperatures. This test facility, which is constructed of ferritic/martensitic steel (Fe-9Cr-1Mo), simulates conditions projected for a liquid metal heat transport system. The test facility will provide test velocities to 0.5 m/s, and temperatures to 550 °C, and system ΔTs up to 150 °C. The corrosion test region simulates the blanket region with a low inlet temperature and a higher (ΔT ~ 150 °C) outlet temperature. Test specimens in the deposition region provide a measure of the deposition processes that will occur in a heat exchanger as the liquid metal is cooled (ΔT ~ 150 °C). In addition to temperature and flow control, the facility provides for control and monitoring of impurities in the liquid.

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