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Title: Development of tritium breeding blankets for DT-burning fusion reactors

Conference ·
OSTI ID:6377863

This study examines the status of understanding of blanket tritium recovery and the performance of potentially viable tritium breeding materials under conditions anticipated in a DT-fueled fusion reactor environment. The existing physicochemical, thermophysical, and ceramographic data for candidate liquid and solid breeders are reviewed and appropriate operating conditions defined. It is shown that selection of a breeding material and an appropriate tritium recovery method can impose significant constraints upon blanket design, particularly when considerations of breeder/coolant/structure compatibility and temperature limitations are taken into account.

Research Organization:
Argonne National Lab., IL (USA)
DOE Contract Number:
W-31-109-ENG-38
OSTI ID:
6377863
Report Number(s):
CONF-801011-92; ON: DE81023904; TRN: 81-013024
Resource Relation:
Conference: 4. ANS topical meeting on the technology of controlled nuclear fusion, King of Prussia, PA, USA, 14 Oct 1980
Country of Publication:
United States
Language:
English