Plasmas With Cold Blankets

Engelmann, F.; Goedheer, W. J.; Nocentini, A.; Schüller, F. C.

doi:10.1016/b978-0-08-021989-9.50079-8

Cited by 7 publications

(12 citation statements)

References 36 publications

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“…As this is a resonant reaction, the rate coefficient of these processes is high. We use [6] ex (cm 3 s" 1 ) <a_v> * 1.25x10-8 {1 -0.17 1 0 log 1} (I) 3 * (1) where n is the reduced mass of the colliding particles in atomic mass units and T is the temperature of the particles in eV.…”

Section: Charge Exchangementioning

confidence: 99%

“…For collisional transport of plasma, the mass difference between deuterons and tritons leads to a rather large isotope separation, i.e. the heavier particles accumulate in the cool part of the plasma [ 1 ]. This effect is particularly strong in the Pfirsch-Schluter regime and weakens as the collisionality of the plasma increases [2].…”

Section: Introductionmentioning

confidence: 99%

“…The second subject treated is related to the removal of helium from a reactor plasma. It has been argued [ 1 ] that, apart from other advantages, a cool plasma/gas blanket surrounding the plasma column provides the possibility of exhausting the helium produced by recombination of fusion-generated alpha particles. The basic argument is the theoretical prediction that in a hydrogen plasma the much heavier alpha particles tend to diffuse outwards.…”

Section: Introductionmentioning

confidence: 99%

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Transport properties of a deuterium, tritium, helium plasma/gas mixture

Potters

Goedheer

1985

Nucl. Fusion

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The paper discusses a numerical model for radial transport in a toroidal plasma/gas mixture consisting of all charge states of deuterium, tritium and helium. Solutions of the steady-state momentum and particle balances indicate an enrichment of tritium gas near the reactor wall compared with deuterium. The helium enrichment ratio, although depending strongly on the ion transport model adopted, is always less than unity. Therefore, pumping helium from a cool plasma/gas blanket surrounding the entire plasma body is not attractive.

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Section: Charge Exchangementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Transport properties of a deuterium, tritium, helium plasma/gas mixture

Potters

Goedheer

1985

Nucl. Fusion

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“…Of the various concepts, e.g. [9][10][11], the divertor has proved so far to be the most promising. The ability of the divertor to control impurities was first demonstrated on the smaller devices DIVA [12] and DITE [2].…”

Section: Introductionmentioning

confidence: 99%

Radiation losses and global energy balance for Ohmically heated discharges in ASDEX

1982

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Global energy balance, radiation profiles and dominant impurity radiation sources are compared for Ohmically heated limiter and divertor discharges in the ASDEX tokamak. In discharges with a poloidal stainless-steel limiter, total radiation from the plasma is the dominant energy loss channel. The axisymmetric divertor reduces this volume-integrated radiation to 30-35% of the heating power and additional Ti-gettering halves it again to 10-15%. Local radiation losses in the plasma centre, which are mainly due to the presence of iron impurity ions, are reduced by about one order of magnitude. In high-current (I p = 400 kA) and high-density (n e = 6 X 10 13 cm" 3 ) ungettered divertor discharges, up to 55% of the heating power is dumped into a cold-gas target inside the divertor chambers. The bolometrically detected volume power losses in the chambers can mainly be attributed to neutral hydrogen atoms with kinetic energies of a few eV. In this parameter range, the divertor plasma is dominated by inelastic molecular and atomic processes, the main process being Franck-Condon dissociation of H 2 molecules.

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“…For D, T discharges these have to be lower than for hydrogen discharges. This corresponds to a cold gas or a cold plasma blanket ; however, it is not yet clear whether this shift of the temperature gradient from the plasma wall transition into the plasma or gas near the wall can be achieved [86].…”

Section: Summary and Conclusion For Plasma Experiments And Later Fusmentioning

confidence: 99%

Boundary Conditions for a Fusion Plasma

Behrisch¹

1977

J. Phys. Colloques

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The boundary conditions in today's plasma experiments and in later fusion plasmas are determined by the interactions of the plasma with the first solid wall. In today's experiments desorption by the plasma hitting the wall dominates, but ion backscattering, trapping and release, as well as sputtering of wall material, will dominate in machines with cleaner walls. The fluxes to the first wall for some of today's plasma experiments are reported and the data about the elementary processes at the first wall are shortly reviewed

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Plasmas With Cold Blankets

Cited by 7 publications

References 36 publications

Transport properties of a deuterium, tritium, helium plasma/gas mixture

Transport properties of a deuterium, tritium, helium plasma/gas mixture

Radiation losses and global energy balance for Ohmically heated discharges in ASDEX

Boundary Conditions for a Fusion Plasma

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