Modeling of edge control by ergodic fields in DIII-D, JET and ITER
Description
The reduction of the heat and particles loads on the Plasma Facing Components (PFCs) due to Type I Edge Localized Modes (ELMs) remains a significant research problem for the international tokamak program. Among the possible approaches of ELMs control is the use of an external perturbing coils to ergodise the edge magnetic fields, thereby increasing the thermal and particle losses in the region of the H-mode barrier and ensuring that the pressure gradient required to trigger Type I ELMs is never attained. A resonant magnetic perturbation (RMP) generated by I-coils in DIII-D has been proven to be able to suppress the type I ELMs reliably without significant degradation of plasma confinement [R. Moyer, et al., Phys. of Plasmas 12, 05611 (2005)]. The paper presents recent modeling results of the Type I ELMs control using stochastic boundaries for the possible future ITER and JET control systems using the realistic experiment in DIII-D as a reference case. A number of possible designs of the external and in-vessel coils ITER are analyzed taking into account physical, technical and space constraints. For typical H-mode scenario and six upper and six lower coils (n=3) configuration ∼400 kA current is needed for external coils and ∼20 kA for in-vessel coils mounted on the blanket modules in order to generate DIII-D-like magnetic perturbation spectrum in ITER. The heat transport and Type I ELMs suppression modelling in the presence of the external magnetic perturbation was done using non-linear code TELM [M. Becoulet, et al., Nucl. Fusion, 45 (2005) 1284] for DIII-D, JET and ITER. The mechanism of the increased heat transport in ergodic fields is the appearance of a radial component of the heat flux parallel to the field lines, due to the radial component of the magnetic field. The first results based on the nonlinear MHD modeling in X-point geometry [G. Huysmans, Plasma Phys. Control Fus. 47 (2005) 2107] taking self-consistent plasma response on the external magnetic perturbation are presented. The most important mechanism of the pressure reduction in the presence of the magnetic perturbation identified is the plasma density transport due to the E x B drift. It was demonstrated that an amplification of the external magnetic perturbation is possible near the threshold for tearing modes. (author)
Additional details
Publishing Information
- Imprint Title
- 21. IAEA fusion energy conference. Book of abstracts
- Imprint Pagination
- 226 p.
- Journal Page Range
- p. 149
- Report number
- IAEA-CN--149
Conference
- Title
- 21. IAEA fusion energy conference
- Dates
- 16-21 Oct 2006
- Place
- Chengdu (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37103049
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTROL; CONTROL SYSTEMS; DISTURBANCES; DOUBLET-3 DEVICE; EDGE LOCALIZED MODES; FIRST WALL; H-MODE PLASMA CONFINEMENT; HEAT FLUX; HEAT TRANSFER; ITER TOKAMAK; JET TOKAMAK; MAGNETIC FIELDS; MAGNETOHYDRODYNAMICS; NONLINEAR PROBLEMS; PARTICLE LOSSES; PLASMA; PLASMA DENSITY; PLASMA SIMULATION; PRESSURE GRADIENTS; RADIATION TRANSPORT; TEARING INSTABILITY; THERMONUCLEAR REACTOR MATERIALS
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; ENERGY TRANSFER; FLUID MECHANICS; HYDRODYNAMICS; INSTABILITY; LOSSES; MAGNETIC CONFINEMENT; MATERIALS; MECHANICS; PLASMA CONFINEMENT; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Secondary number(s)
- IT/P1--29