CONCEPTUAL DESIGN OF AN ELECTRICITY GENERATING TRITIUM BREEDING BLANKET SECTOR FOR INTOR - NET
This study of a fusion reactor power blanket and its associated equipment had the objective of producing a conceptual design for a blanket sector of INTOR, or one of its national variants (e.g. NET), from which electricity could be generated simultaneously with the breeding of tritium. A honeycomb blanket structure of stainless steel supports solid breeder elements of lithium metasilicate and beryllium neutron multiplier. These are cooled by helium at a pressure of 50 bar. The helium at an outlet temperature of 580 degrees C, raises steam at 500 degrees C and at a pressure of 170 bar, which is delivered to a 7 MW(e) turbogenerator. Tritium diffuses continuously from the breeder material into the main helium coolant stream and is extracted from a circuit which samples a small fraction of the flow. A local tritium breeding ratio of about 1.26 is achieved, together with a blanket coverage of the plasma of about 60 %. It is concluded that such a blanket design would be feasible after some reasonable developments in current technology.
Bibliographic Reference: WRITE TO THE LIBRARIAN, UKAEA, CULHAM LABORATORY, ABINGDON, OXON. OX14 3DB, (UK), MENTIONING REPORT CLM P-718, 1984
Record Number: 1989123032100 / Last updated on: 1987-01-01
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