Modelling radiative power exhaust in view of DEMO relevant scenarios
Creators
- 1. Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, 52425 Jülich (Germany)
- 2. Max-Planck-Institut für Plasmaphysik, 85748 Garching bei München (Germany)
- 3. Aalto University, Espoo (Finland)
Description
Power exhaust in future electricity producing fusion device features difficulties which, compared to ITER, are harder to tackle in terms of operational control requiring an improved physics understanding. Primarily, the heat flux problem must be solved in order to allow plasma facing components (PFCs) to withstand a maximum heat flux not exceeding 5MW/m2 in steady state on timescales lasting days or weeks. For a given Ploss/R, with Ploss being the power arriving from the core into the pedestal region, a total dissipated fraction fdiss=Pdiss/Ploss close to 95% or higher is required to reduce the total target heat load qt . Pdiss covers the diverted plasma edge region, the full scrape-off layer (SOL) and parts of the confined core region and thus accounts for losses from (impurity) radiation, transport towards the main-chamber and charge-exchange collisions with neutrals.
Additional details
Identifiers
Publishing Information
- Imprint Title
- 2nd IAEA Technical Meeting Divertor Concepts. Programme and Book of Abstracts
- Imprint Pagination
- 80 p.
- Journal Page Range
- p. 15-16
- Report number
- INIS-XA--21M3794
Conference
- Title
- 2. IAEA Technical Meeting on Divertor Concepts
- Acronym
- DC 2017
- Dates
- 13-16 Nov 2017
- Place
- Suzhou (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52124438
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S71: CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHARGE EXCHANGE; COMPUTERIZED SIMULATION; ELECTRICITY; ELECTRON COLLISIONS; FIRST WALL; HEAT; HEAT FLUX; HEATING LOAD; IMPURITIES; ITER TOKAMAK; PLASMA; PLASMA SCRAPE-OFF LAYER; RADIATION TRANSPORT; SOLS; STEADY-STATE CONDITIONS
- Descriptors DEC
- BOUNDARY LAYERS; CLOSED PLASMA DEVICES; COLLISIONS; COLLOIDS; DISPERSIONS; ENERGY; LAYERS; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS