Abstract
Experiments on DIII-D confirm that the tritium breeding test blanket modules (TBMs) in ITER will lead to a decrease of the plasma rotation in H-modes [M.J. Schaffer, et al., Nucl. Fusion 51 (2011) 103028]. Moreover, they suggest that long-wavelength correction fields applied with non-axisymmetric saddle coils will only be able to ameliorate a fraction of such a rotation reduction. The new finding obtained in rotating H-modes with parameters similar to the ITER baseline scenario contrasts previous experiments, which showed that saddle coils are very effective in restoring resilience to locked modes in L-mode plasmas. The experiments use a TBM mock-up coil that has been especially designed to simulate the error field induced by the ferromagnetic steel of a pair of TBMs in one ITER port. The n = 1 error field correction (EFC) is applied with a set of non-axisymmetric saddle coils (I-coil), whose currents are optimized in the presence of the TBM mock-up field using a newly developed non-disruptive technique that maximizes the angular momentum. However, a test of the effectiveness of the TBM EFC yields that the optimized EFC can only recover approximately a quarter of the ~20% rotation decrease attributed to the TBM error field. An alternative criterion to evaluate EFC has been its effectiveness in canceling the n = 1 plasma response to the field error. Plasma response measurements in the TBM experiment show that the I-coil can indeed cancel the magnetic measurements of the n = 1 plasma response to the TBM mock-up field. The required currents agree within the uncertainties of the estimates with the currents that maximize the angular momentum. The contrast between the limited effectiveness of n = 1 EFC in rotating H-modes and their ability to recover a low locking density in L-mode plasmas shows that the components of the non-axisymmetric field that brake the plasma at higher values of beta or higher rotation differ from the components that are responsible for the field penetration in low density L-modes.
| Original language | English |
|---|---|
| Title of host publication | Programme, Abstracts, Presentations & Proceedings |
| Subtitle of host publication | 24th IAEA Fusion Energy Conference, October 8-13, 2012, San Diego, USA |
| Publisher | International Atomic Energy Agency IAEA |
| Number of pages | 8 |
| Publication status | Published - 2012 |
| MoE publication type | A4 Article in a conference publication |
| Event | 24th IAEA Fusion Energy Conference - San Diego, United States Duration: 8 Oct 2012 → 13 Oct 2012 http://www-naweb.iaea.org/napc/physics/FEC/FEC2012/html/proceedings.pdf (Full proceedings) |
Conference
| Conference | 24th IAEA Fusion Energy Conference |
|---|---|
| Country/Territory | United States |
| City | San Diego |
| Period | 8/10/12 → 13/10/12 |
| Internet address |
|
UN SDGs
This output contributes to the following UN Sustainable Development Goals (SDGs)
-
SDG 7 Affordable and Clean Energy
Fingerprint
Dive into the research topics of 'Rotation Braking and Error Field Correction of the Test Blanket Module Induced Magnetic Field Error in ITER'. Together they form a unique fingerprint.Cite this
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver