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An outline of application to a fusion driver is also presented.
Solenoid transport of high current, heavy ion beams is considered for several stages of a heavy ion fusion driver.
Despite a partial replacement of the lithium zone by the fissile zone, tritium breeding remains still >1.05, which will be required for a self-sustaining fusion driver.
The methods and codes employed in the US Heavy Ion Fusion program to simulate the beams in an Integrated Research Experiments IREE) facility and a fusion driver are presented in overview.
Values of tritium breeding ratio (TBR), which is another important parameter in a fusion fission hybrid reactor, are about 1.2 for all investigated cases so that tritium self-sufficiency is maintained for (D,T) fusion driver.
The tritium breeding ratio is greater than 1.05 for all investigated fuel types and the hybrid reactor is self-sufficient in the tritium required for the (DT) fusion driver in those modes during the operation period.
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Designs for heavy ion fusion drivers call for beam brightness and intensity surpassing traditional limits.
The heavy-ion fusion program is conducting several ion source and injector experiments to support ongoing HIF beam transport experiments and to develop new injector concepts for future fusion drivers.
In this paper we report on two Heavy Ion Fusion (HIF) driver point design studies.
With the new concept of indirectly driven targets for heavy ion inertial fusion, the driver scenarios had to be reconsidered.
The fusion-driven subcritical system (FDS-I) which consists of the fusion neutron driver with feasible and easy-achieved plasma parameters and the multifunctional subcritical blanket (DWT) was proposed as an intermediate step toward the final application of fusion energy.
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