Novel Radiofrequency Current Drive Systems for Fusion Plasma Sustainment on DIII-D
- 1. Plasma Science and Fusion Center, MIT, Cambridge, MA 02139 (United States)
- 2. General Atomics, San Diego, CA 92186 (United States)
Description
Full text: The DIII-D National Fusion Facility is advancing the science and technology of steadystate fusion plasma sustainment through the implementation of two first-of-a-kind radio frequency current drive systems. the "helicon" or fast wave in the lower hybrid range of frequencies (LHRF), and high field side (HFS) launch of the lower hybrid slow wave. Using existing DIII-D discharges, we have identified high performance scenarios that are predicted to have excellent wave penetration, strong single pass absorption and high current drive efficiency. Simulations predict this will raise ideal βN limits in DIII-D and permit access to higher density advanced tokamak regimes. The higher B-field on the HFS improves wave accessibility and allows for use of lower n‖, resulting in higher current drive efficiency for LHRF slow waves and damping at r/a ∼ 0.6–0.8 on the first pass. The 476 MHz helicon has better accessibility at lower B-field and higher density than the 4.6 GHz slow wave due to the lower frequency that can be used for the fast wave. Calculations show that HFS launch of slow waves in the LHRF can lead to a physics current drive efficiency of 0.17 x 1020 A/W*m2 at r/a ∼ 0.6–0.8 in DIII-D and 0.4 x 1020 in a high B-field reactor. HFS LHRF represents an integrated solution that both improves core wave physics and mitigates PMI/coupling issues. An innovative, compact HFS LHRF antenna design has been developed combining a slotted waveguide poloidal splitter (used on CMod) and multijunction toroidal splitter (used on Tore Supra, EAST). Models show good coupling properties for predicted edge density profiles. Current drive by helicons is predicted to be significantly more efficient than either off-axis neutral beam current drive or conventional ECCD in high-density, high electron- regimes. A 12-module helicon antenna was developed and tested in DIII-D and demonstrated sufficient coupling at < 0.4 kW. A ∼ 1 MW proof-of-principle experiment using helicon waves at 476 MHz launched with a novel "comb-line" travelling wave antenna with 30 elements will be performed on DIII-D starting in 2019. Work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using User Facility DIII-D, under Award Number DE-FC02-04ER54698 and by U.S. Department of Energy Contract No. DE-FC02-01ER54648 under Scientific Discovery through Advanced Computing. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
- Imprint Pagination
- 844 p.
- Journal Page Range
- p. 585
- Report number
- IAEA-CN--258
Conference
- Title
- 27. IAEA Fusion Energy Conference
- Acronym
- FEC 2018
- Dates
- 22-27 Oct 2018
- Place
- Ahmedabad (India)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50071235
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ABSORPTION; ANTENNAS; AWARDS; BEAM CURRENTS; DOUBLET-3 DEVICE; ECR CURRENT DRIVE; EFFICIENCY; GHZ RANGE; HELICON WAVES; LOWER HYBRID CURRENT DRIVE; LOWER HYBRID HEATING; MHZ RANGE; PLASMA; RADIOWAVE RADIATION; SIMULATION; THERMONUCLEAR REACTORS; TORE SUPRA TOKAMAK; TRAVELLING WAVES
- Descriptors DEC
- CLOSED PLASMA DEVICES; CURRENTS; ELECTRICAL EQUIPMENT; ELECTROMAGNETIC RADIATION; EQUIPMENT; FREQUENCY RANGE; HEATING; HIGH-FREQUENCY HEATING; NON-INDUCTIVE CURRENT DRIVE; PLASMA HEATING; RADIATIONS; SORPTION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Contract/Grant/Project number
- Contract DE-FC02-04ER54698; DE-FC02-01ER54648
- Secondary number(s)
- IAEA-CN--258-372