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Isotopic tailoring of the deuterium and tritium density profiles in fusion reactors can lead to reduced tritium inventory in plasma facing components and, therefore, improved safety considerations. The isotopic tailoring concept consists of utilizing a tritium-rich pellet source for core fueling and a deuterium-rich gas source for edge fueling. Because of(More)
Integrated simulation of magnetically confined fusion has long been recognized as a major milestone towards feasible fusion reactor designs. Such simulations involve a myriad of physics processes that span spatio-temporal scales spanning many orders of magnitudes. The fusion community has long relied on balkanized stand alone code basis to simulate(More)
COMPACT IGNITION TOKAMAK PHYSICS AND ENGINEERING BASIS. The Compact Ignition Tokamak (CIT) is a high-Beld, compact tokamak design whose objective is the study of physics issues associated with burning plasmas. The toroidal and poloidal field coils employ a copper-steel laminate, mamrfacmred by explosive-bonding techniques, to support the forces generated by(More)
Peaked density profiles may not only improve confinement properties, but also give the additional benefits of increased fusion production and ignition margin in BPX, as shown in Fig. 8.1. The ability to control density profiles in the core and scrape-off regions is governed by a number of both physics and operational considerations that make it difficult to(More)
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