A TRITIUM BREEDING AND ELECTRICITY GENERATING BLANKET SECTOR FOR INTOR - NET
This study of a fusion reactor power blanket and associated equipment had the objective of a demonstration experiment in INTOR or in one of its national variants (eg NET). A honeycomb blanket structure of stainless steel supports breeder elements which contain lithium metasilicate and a beryllium neutron multiplier. These are cooled by helium at 50 bar. Tritium extractions is continuous; it diffuses from the breeder into the helium circuit and a small fraction of the total flow is processed in a molecular sieve system. A local breeding ratio of about 1.26 is achieved together with a blanket coverage of 60 %. For a self sufficient section 80 % coverage would be required. Helium at 580 degrees C raises steam at 500 degrees C and 170 bar which is delivered to a 7 MWE-(el) turbogenerator. No account was taken of the heat generated in the first wall and the divertor because these were the subjects of the specialist study within the INTOR/NET project.
Bibliographic Reference: 10TH SYMPOSIUM ON FUSION ENGINEERING, PHILADELPHIA (USA), DEC. 5-9, 1983 VOL. 1, PP. 238-243 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31961 ORA
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Record Number: 1989123044800 / Last updated on: 1987-01-01
Available languages: en