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T. J. Dolan a, J. C. DeVeaux
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1130-1135
Alternate Fuels and Innovative Confinement Concept | doi.org/10.13182/FST89-A39845
Articles are hosted by Taylor and Francis Online.
The DT fusion neutron yield is calculated as a function of plasma current I for a variety of cases, assuming that the plasma temperature scales as To = Tr(I/Ir)y(ar/a)x where subscripts r denote reference values, and x and y are scaling parameters. The first-wall minor radius a is limited by the tolerable heat flux q. If β = 15 %, R = 4 m, I = 10 MA, and q = 3 MW/m2, then a = 0.43 m, and the 14 MeV neutron current at the first wall is about 1018 neutrons/m2s. a Work begun at Phillips Research Center. On leave from the University of Missouri-Rolla.