Stability and Performance of ITER Steady State Scenarios with ITBs
Description
Full text: Steady state scenarios envisaged for ITER aim at optimizing the bootstrap current drive, while maintaining sufficient confinement and stability to provide the necessary fusion yield. Non- inductive steady state scenarios on ITER will need to operate with Internal Transport Barriers (ITBs) in order to reach adequate fusion gain at typical currents of 9 MA. We have analyzed the ideal MHD stability of steady state scenarios that use 8 — 33 MW of Neutral Beam with addition of different mixtures of external heating, namely 20 — 40 MW of EC, 20 — 40 MW of LH and 5 — 20 MW of IC. Target plasmas have H98 ∼1.6, which is necessary to access 100% non-inductive current in the range of 7 — 10 MA and fusion yield of Q ∼ 3 — 6 [1]. These configurations are established as relaxed flattop states with time-dependent transport simulations, which have been run with TSC [2]. The sensitivity of n = 1, 2 kink (with and without a wall) and n = ∞ ballooning instabilities has been analyzed against variations of the pressure profile peaking between 2.3 and 2.9, and of the Greenwald fraction up to 1.2. It is found that LH heating is desirable to maintain the safety factor profile above 1.5. By operating with broad pressure profiles and ITBs at 2/3 of the minor radius, plasmas with 33 MW of NB and 40 MW of LH have qmin > 2, are ideal MHD stable and can achieve βN > 4li with an ideal wall. The EC provides localized heating and current drive profiles, but 40 MW of EC raise the self-inductance and drive qmin down below 1.5, driving n = 1 and n = 2 kinks instabilities. The stability of these configuration can be improved for deposition outside ρ(qmin) = 0.35. The trade-off of current drive efficiency vs ideal MHD stability with ρ(qmin) will be discussed, with focus on the effectiveness of the upper launcher in controlling the current profile. References [1] Kessel CE et al., Development of ITER Advanced Steady State and Hybrid Scenarios, IAEA Fusion Energy Conference 2010. (author)
Additional details
Publishing Information
- Imprint Title
- 24. IAEA Fusion Energy Conference. Programme and Book of Abstracts
- Imprint Pagination
- 789 p.
- Journal Page Range
- p. 578
- Report number
- IAEA-CN--197
Conference
- Title
- 24. IAEA Fusion Energy Conference
- Acronym
- FEC 2012
- Dates
- 8-13 Oct 2012
- Place
- San Diego, CA (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45033997
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BALLOONING INSTABILITY; BOOTSTRAP CURRENT; CHARGED-PARTICLE TRANSPORT; FUSION YIELD; HEATING; ITER TOKAMAK; KINK INSTABILITY; MAGNETOHYDRODYNAMICS; MIXTURES; SIMULATION; STABILITY; STEADY-STATE CONDITIONS; THERMAL BARRIERS; TIME DEPENDENCE
- Descriptors DEC
- CLOSED PLASMA DEVICES; CURRENTS; DISPERSIONS; ELECTRIC CURRENTS; FLUID MECHANICS; HYDRODYNAMICS; INSTABILITY; MECHANICS; NUCLEAR REACTION YIELD; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; RADIATION TRANSPORT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YIELDS
Optional Information
- Contract/Grant/Project number
- Contract DE-AC02-CH0911466
- Notes
- 1 ref.
- Secondary number(s)
- ITR/P1--21