This paper presents the results of a multi-system codes benchmarking study of the recently published China Fusion Engineering Test Reactor (CFETR) pre-conceptual design (Wan et al 2014 IEEE Trans. Plasma Sci. 42 495). Two system codes, General Atomics System Code (GASC) and Tokamak Energy System Code (TESC), using different methodologies to arrive at CFETR performance parameters under the same CFETR constraints show that the correlation between the physics performance and the fusion performance is consistent, and the computed parameters are in good agreement. Optimization of the first wall surface for tritium breeding and the minimization of the machine size are highly compatible. Variations of the plasma currents and profiles lead to changes in the required normalized physics performance, however, they do not significantly affect the optimized size of the machine. GASC and TESC have also been used to explore a lower aspect ratio, larger volume plasma taking advantage of the engineering flexibility in the CFETR design. Assuming the ITER steady-state scenario physics, the larger plasma together with a moderately higher BT and Ip can result in a high gain Qfus ∼ 12, Pfus ∼ 1 GW machine approaching DEMO-like performance. It is concluded that the CFETR baseline mode can meet the minimum goal of the Fusion Nuclear Science Facility (FNSF) mission and advanced physics will enable it to address comprehensively the outstanding critical technology gaps on the path to a demonstration reactor (DEMO). Before proceeding with CFETR construction steady-state operation has to be demonstrated, further development is needed to solve the divertor heat load issue, and blankets have to be designed with tritium breeding ratio (TBR) >1 as a target.
Detailed studies of sawtooth activity in Ohmic plasmas in JET have revealed significant discrepancies both with previously reported observations of the phenomenon and with conventional models of the internal disruption. ‘Compound’ sawteeth, which display an intermediate collapse during the ramp phase, are observed in the majority of discharges. These usually exhibit no precursor activity, in contrast to observations in smaller tokamaks, but are often accompanied by successor oscillations. Furthermore, the collapse time of such sawteeth is much shorter than expected. These results suggest that the conventional model of the sawtooth is inadequate to explain sawtooth activity in large tokamaks.
Tokamak Energy Ltd, UK, is developing spherical tokamaks using high temperature superconductor magnets as a possible route to fusion power using relatively small devices. We present an overview of the development programme including details of the enabling technologies, the key modelling methods and results, and the remaining challenges on the path to compact fusion.
Astract. The change in thermal transport aaoss the L + H transition is studied in detail for those JET high performance H-modes which have a very fast transftion. It is found that in these pulses the transport changes very rapidly (< 4 msecs) over a very large radial region 0.5 < p < 1, and a very large transport barrier is formed. The reasons for the formation of this barrier are discussed.
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