Assessment of the Runaway Electron Energy Dissipation in ITER
Creators
- 1. National Research Centre "Kurchatov Institute", Moscow (Russian Federation)
- 2. Max-Planck-Institut für Plasmaphysik, Greifswald (Germany)
- 3. Keldysh Institute of Applied Mathematics, RAS, Moscow (Russian Federation)
- 4. International Thermonuclear Experimental Reactor (ITER), Cadarache Centre, 13108 Saint-Paul-lès-Durance (France)
- 5. Max-Planck-Institut für Plasmaphysik, Garching (Germany)
Description
Full text: A substantial fraction of the plasma current can be converted into runaway electron (RE) current in ITER disruptions. During the RE plateau stage of the disruption, the kinetic energy of a runaway beam is expected to be much smaller than the magnetic one. However, at the following current termination phase, the electric field induced due to the RE loss to the wall causes the generation of new and acceleration of existing REs. Thus, some fraction of the initial plasma magnetic energy can be converted into RE kinetic energy. Preceding studies predicted significant, up to ∼100%, conversion of the magnetic energy into kinetic one during the RE current termination phase of disruptions, i.e., when the majority of REs are lost. In the present report we assess the RE energy dissipation with the DINAdisruption simulator appended with the new RE kinetic model based on the analytical solutions of the RE kinetic equation. The new kinetic model allows for the direct evaluation of RE kinetic energy lost to the wall due to plasma scrapping off at final stage of vertical displacement event (VDE). Generation of the halo currents was found to significantly reduce the conversion of RE magnetic into kinetic energy. Further suppression of RE regeneration at the plasma periphery is seen when an effective losses of REs are introduced in a narrow layer near the plasma boundary, mimicking the effect of external perturbations of the magnetic field. Sensitivity studies of the RE energy deposited to the wall are performed with variation of the amplitude and radial profile of the RE seed current at the beginning of the current quench (CQ). In addition, the simulations of the CQ with REs are accompanied by ideal and resistive MHD stability analysis, which allows identifying the RE plasma stability boundary and to estimate the value and radial profile of the RE loss time. Finally, the mitigation of RE by injection of impurity during RE plateau is simulated with various impurity quantity and delivery time dependence as expected for massive gas or shattered pellet injection techniques. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
- Imprint Pagination
- 935 p.
- Journal Page Range
- p. 474
- Report number
- IAEA-CN--234
Conference
- Title
- 26. IAEA Fusion Energy Conference
- Acronym
- FEC 2016
- Dates
- 17-22 Oct 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49093348
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMPLITUDES; ANALYTICAL SOLUTION; DISTURBANCES; ELECTRIC CURRENTS; ELECTRIC FIELDS; ENERGY LOSSES; IMPURITIES; ITER TOKAMAK; KINETIC ENERGY; KINETIC EQUATIONS; KINETICS; MAGNETIC FIELDS; MAGNETOHYDRODYNAMICS; PELLET INJECTION; PLASMA; RUNAWAY ELECTRONS; SENSITIVITY ANALYSIS; TIME DEPENDENCE
- Descriptors DEC
- CLOSED PLASMA DEVICES; CURRENTS; ELECTRONS; ELEMENTARY PARTICLES; ENERGY; EQUATIONS; FERMIONS; FLUID MECHANICS; HYDRODYNAMICS; LEPTONS; LOSSES; MATHEMATICAL SOLUTIONS; MECHANICS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- Abstract only; 1 ref.
- Secondary number(s)
- IAEA-CN--234-0321