SOME CONSIDERATIONS ON TRITIUM CONTROL IN A HELIUM COOLED CERAMIC BLANKET FOR THE NET REACTOR
Since 1983 the Karlsruhe Nuclear Research Center is investigating the technological problems of helium cooled ceramic blankets for fusion reactors. Various solutions have been so far investigated: poloidal, toroidal or lobular arrangement of the pressure tubes containing the breeder material and the cooling of helium; lead multiplier integral with the first wall or beryllium in the ceramic breeder region. For all these designs it is crucial to maintain the tritium losses from the plant equal or below 10 curie/d. This requires a helium purge flow completely separated from the main helium coolant flow.
Bibliographic Reference: FOR FULL-SIZE VERSION WRITE TO GFK, MENTIONING KFK 3755; FOR MICROFICHE WRITE TO EUROFFICE, LUXEMBOURG, POB 1003, 39 P., BFR 120, MENTIONING EUR 7993 EN, MF (1984)
Availability: Can be ordered online
Record Number: 1989122083800 / Last updated on: 1987-01-01
Available languages: en