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Hubbard, A.E.; Brunner, D.; Cziegler, I.
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material2018
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material2018
AbstractAbstract
[en] Full text: Significant progress has been made on Alcator C-Mod in expanding the configurations and conditions for which the I-mode regime can be accessed and maintained and understanding the physics which underlies the transport improvement. An important result from multi device studies is that the power threshold for I-mode has only a weak dependence on Bt, while the upper power limit increases with Bt, making I-modes more robust at higher field. Experiments in 2015 have extended this trend, achieving clear I-modes at up to 8.0 T. The I-mode regime is naturally stable to ELMs, and combines high τE with low particle confinement. This has benefits for fusion reactors, eliminating damaging ELM heat pulses and avoiding impurity accumulation. The τE in I-mode is in the H-mode range and has weak power degradation ~P-0.3. ELITE analysis shows the pedestal to be stable, consistent with this lack of saturation and the absence of ELMs. Nonlinear GYRO simulations show that I-mode core Ti and Te profiles are stiffer than in L-mode, resembling H-mode with regards to marginal ITG stability. Imode pedestal physics is also advancing, through measurements of fluctuations and flows and using simulations. Both a GAM and a high frequency fluctuation termed theWeakly Coherent Mode are present and strongly interact. Nonlinear BOUT++ simulations agree with many observed features of theWCM. The C-Mod team has been exploring prospects for extrapolation of I-mode to larger fusion devices. We predict ITER would need about 70 MW to enter I-mode. It should be possible to remain in I-mode and to produce high fusion power, provided that density can be sufficiently increased. Accessibility for compact, high-B fusion reactors such as ARC is even more favourable. We are also investigating integration with divertor solutions. Mitigating heat flux using low-Z impurity seeding has been demonstrated, and we have begun to investigate divertor detachment strategies. While robust I-mode operation is typically achieved with ion B x ∇B drift away from the X-point, new experiments show that after the L-I transition, the regime can be maintained in a DN configuration. This may help to reduce peak heat flux. Further I-mode experiments will be a priority in 2016. (author)
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International Atomic Energy Agency, Division of Physical and Chemical Sciences, Vienna (Austria); 935 p; 3 May 2018; p. 175; FEC 2016: 26. IAEA Fusion Energy Conference; Kyoto (Japan); 17-22 Oct 2016; IAEA-CN--234-0366; Available as preprint from https://nucleus.iaea.org/sites/fusionportal/Shared%20Documents/FEC%202016/fec2016-preprints/preprint0366.pdf; PowerPoint presentation available from https://nucleus.iaea.org/sites/fusionportal/Shared%20Documents/FEC%202016/fec2016-material/material0366.pdf; Abstract only; 2 refs.
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