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Abstract

Neutronic and heat transfer calculations have been performed for two helium cooled blankets for the INTOR design. The neutronic calculations show that the local tritium breeding ratios, both for the ceramic blanket (Li-2SiO-3) and for the liquid blanket(Li-17Pb-83) solutions, are 1.34 for natural tritium and about 1.45 using 30 % Li**6 enrichment. The heat transfer calculations show that it is possible to cool the divertor section of the torus (heat flux = 1.7 MW/m**2) with helium with an inlet pressure of 52 bar and an inlet temperature of 40 degrees C. The temperature of the back face of the divertor can be kept at 130 degrees C. With helium with the same inlet conditions it is possible to cool the first wall as well (heat flux = 0.136 MW/m**2) and keep the back face of this wall at a temperature of 120 degrees C. The arrangement proposed for the ceramic blanket with the breeder contained in perforated tubes promises an effective helium mass exchange between the breeder bed and the main helium flow. This, together with the possibility of keeping an extremely low level of impurities in the primary helium circuit, suggests that the tritium inventory of the coolant helium should be very small (of the order of a few grams).

Additional information

Authors: DALLE DONNE M, KERNFORSCHUNGSZENTRUM KARLSRUHE GMBH (GERMANY);DORNER S, KERNFORSCHUNGSZENTRUM KARLSRUHE GMBH (GERMANY);TACZANOWSKI S KERNFORSCHUNGSZENTRUM KARLSRUHE GMBH (GERMANY), KERNFORSCHUNGSZENTRUM KARLSRUHE GMBH (GERMANY)
Bibliographic Reference: FOR FULL-SIZE VERSION - WRITE TO GFK MENTIONING KFK 3584; FOR MICROFICHE - WRITE TO, EUROFFICE, LUXEMBOURG, POB 1003, 60 P., BFR 120, MENTIONING EUR 7987 EN, MF (1983)
Availability: Can be ordered online
Record Number: 1989122038400 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en
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