Published: Jan 2001
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This chapter is primarily devoted to considerations of the oxidation, corrosion, and compatibility of the high-chromium martensitic steels in environments currently appropriate for D-T tokamak fusion power reactors, namely water coolant, liquid lithium and lithium-lead eutectic (Li17Pb83) coolants and/or tritium breeders, solid ceramic tritium breeding materials, and beryllium neutron multiplier.
Paper ID: MONO10020M