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Steiner, D.; Flanagan, C.A.
Oak Ridge National Lab., TN (USA)1981
Oak Ridge National Lab., TN (USA)1981
AbstractAbstract
[en] The device has a major radius of 5.0 m with a plasma minor radius of 1.3 m elongated by 1.6. Capability is provided for operating the toroidal field coils up to 10 T, but the bulk of the operations are designed for 8 T. At 8-T conditions, the fusion power is approx. 180 MW (neutron wall loading approx. 0.4 MW/m2) and a plasma Q of approx. 5 is expected. At 10-T conditions, which are expected to be limited to about 10% of the total operations, the fusion power is approx. 450 MW (approx. 1.0 MW/m2) and ignition is expected
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Oct 1981; 4 p; 9. symposium on engineering problems of fusion research; Chicago, IL, USA; 26 - 29 Oct 1981; Available from NTIS., PC A02/MF A01
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