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Development of tritium technology for the magnetic fusion energy program

Conference · · Proc. Symp. Eng. Probl. Fusion Res.; (United States)
OSTI ID:6230015
The use of the radioactive hydrogen isotope of mass three (tritium) as a fuel component in fusion reactors introduces several possible problem areas in reactor design. The primary fusion reactors in a D-T plasma is the T(D,n)/sub 4/He reaction with an energy release of approximately 17.5, nMeV. Fuel is bred in fusion reactors and the bred fuel must be removed efficiently from the blanket. A second area of lithium technology is that of fuel reprocessing. Other special problems introduced by tritium are related to radiation damage and chemical compatibility of materials used in tritium facilities. This paper briefly describes the current status of tritium technology in each of these areas.
Research Organization:
Los Alamos Natl Lab, NM, USA
OSTI ID:
6230015
Report Number(s):
CONF-811040-
Conference Information:
Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States)
Country of Publication:
United States
Language:
English