The impact of new experimental data on the design of Pb-17Li/Water breeding blankets

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The Pb-17Li/water-cooled blanket is one of the concepts being developed in Europe for testing in NET (Next European Torus). JRC-Ispra is strongly involved in this development. This paper describes the impact of the latest experimental results on the blanket design. The points considered are:

breeder operating temperature and thermomechanical design: experiments on corrosion with steel 316L and liquid metal embrittlement tests haver provided upper and lower limits for the breeder operating temperature (280–400 °C);

tritium recovery from the breeder and permeation rate to the coolant: Ispra measurements indicate that solubility and diffusivity of hydrogen in Pb-17Li are lower as compared with the previous values used in blanket tritium analyses. The impact of these results on the design of the tritium recovery system is discussed;

accident analyses: the experiments in progress at Ispra on the Pb-17Li/water interaction are reviewed and their application to a coolant pipe break accident is shown.

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