Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO
Creators
- 1. Max Planck Institute for Plasma Physics, EURATOM Association, D-85748 Garching (Germany)
- 2. EFDA PPP and T Department, D-85748 Garching (Germany)
Description
A future fusion reactor is expected to have all-metal plasma facing materials (PFMs) to ensure low erosion rates, low tritium retention and stability against high neutron fluences. As a consequence, intrinsic radiation losses in the plasma edge and divertor are low in comparison to devices with carbon PFMs. To avoid localized overheating in the divertor, intrinsic low-Z and medium-Z impurities have to be inserted into the plasma to convert a major part of the power flux into radiation and to facilitate partial divertor detachment. For burning plasma conditions in ITER, which operates not far above the L–H threshold power, a high divertor radiation level will be mandatory to avoid thermal overload of divertor components. Moreover, in a prototype reactor, DEMO, a high main plasma radiation level will be required in addition for dissipation of the much higher alpha heating power. For divertor plasma conditions in present day tokamaks and in ITER, nitrogen appears most suitable regarding its radiative characteristics. If elevated main chamber radiation is desired as well, argon is the best candidate for the simultaneous enhancement of core and divertor radiation, provided sufficient divertor compression can be obtained. The parameter Psep/R, the power flux through the separatrix normalized by the major radius, is suggested as a suitable scaling (for a given electron density) for the extrapolation of present day divertor conditions to larger devices. The scaling for main chamber radiation from small to large devices has a higher, more favourable dependence of about Prad,main/R2. Krypton provides the smallest fuel dilution for DEMO conditions, but has a more centrally peaked radiation profile compared to argon. For investigation of the different effects of main chamber and divertor radiation and for optimization of their distribution, a double radiative feedback system has been implemented in ASDEX Upgrade (AUG). About half the ITER/DEMO values of Psep/R have been achieved so far, and close to DEMO values of Prad,main/R2, albeit at lower Psep/R. Further increase of this parameter may be achieved by increasing the neutral pressure or improving the divertor geometry. (paper)
Availability note (English)
Available from http://dx.doi.org/10.1088/0741-3335/55/12/124041Additional details
Identifiers
Publishing Information
- Journal Title
- Plasma Physics and Controlled Fusion
- Journal Volume
- 55
- Journal Issue
- 12
- Journal Page Range
- [10 p.]
- ISSN
- 0741-3335
- CODEN
- PPCFET
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46067727
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- ARGON; ASDEX TOKAMAK; CARBON; COMPARATIVE EVALUATIONS; DIVERTORS; ELECTRON DENSITY; EROSION; FIRST WALL; ITER TOKAMAK; KRYPTON; NEUTRON FLUENCE; NITROGEN; PLASMA; PLASMA IMPURITIES; RETENTION; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; ELEMENTS; EVALUATION; FLUIDS; GASES; HYDROGEN ISOTOPES; IMPURITIES; ISOTOPES; LIGHT NUCLEI; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; RARE GASES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Collaborations
- ASDEX Upgrade Team