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Your search keyword '"Pacher, G.W."' showing total 29 results
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29 results on '"Pacher, G.W."'

15. ITER divertor performance in the low-activation phase.

Author

Kukushkin, A.S., Pacher, H.D., Kotov, V., Pacher, G.W., Pitts, R.A., and Reiter, D.

Subjects
PLASMA instabilities, PLASMA physics, HELIUM plasmas, HEAT flux measurement, FUSION reactors, NUCLEAR fusion
Abstract

The paper presents results of SOLPS modelling of the edge plasma performance during the low-activation phase of ITER operation. The calculations show that the peak power loading of the divertor targets can reach the reactor-relevant level of 3 to 5 MW m−2, even without the fusion reactions, rendering commissioning of the high heat flux components possible in this phase. Parametrization of the output of the SOLPS runs for the predominantly helium plasma concerned by the studies reported here is performed, thus providing the boundary conditions for modelling of the core and allowing efficient integration of the core and edge models. This approach, using the ASTRA code for core simulations, is applied to the analysis of hydrogen accumulation in helium plasmas due to H pellet injection. The latter is the only available option for early testing of ELM pace-making as an ELM control tool assuming H-mode in hydrogen will not be possible. Critical dilution with H down to 70% He in the core plasma can be reached in only 0.5 to 1 s or even shorter, depending on the assumptions made. [ABSTRACT FROM AUTHOR]

Published
2013
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16. Impact of potential narrow SOL heat flux on H-mode access in ITER.

Author

Kukushkin, A.S., Pacher, H.D., Pacher, G.W., Kotov, V., Pitts, R.A., and Reiter, D.

Subjects
DIVERTERS (Electronics), PEDESTALS, SURGE arresters, PLASMA core reactors, PLASMA boundary layers, PLASMA physics
Abstract

The paper presents results of a first analysis of the divertor performance during the L–H transition in ITER. The integrated model consists of the SOLPS4.3 code suite for the SOL and divertor, and the ASTRA code for the core and pedestal regions. The results of SOLPS4.3 are parametrized and used as the boundary conditions for ASTRA, ensuring a consistent description of the plasma core and the edge. Boundary conditions switch from those for wide (L-mode) to narrow (H-mode) SOL once the transition criterion is met. The results show that, for conditions for which a full-power operational space with acceptable power loading of the targets exists, a transition from the initial L-mode operation to H-mode can be found for the same assumptions, i.e. the full-power H-mode regime is accessible. [ABSTRACT FROM AUTHOR]

Published
2013
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24. First results on plasma-surface interactions in the tokamak de varennes

Author

Terreault, B., Boucher, C., Paynter, R.W., Ross, G.G., ThÉriault, D., Abel, G., Boivin, R., Bolton, R.A., Castracane, J., Chevalier, G., Couture, P., Décoste, R., Demers, Y., Dimoff, K., Glaude, V., Gregory, B.C., Haddad, E., Janicki, C., Kalnavarns, J., Lachambre, J.L., Mai, H.H., Neufeld, C.R., Pacher, H.D., Pacher, G.W., Richard, N., Saint-Jacques, R.G., Saint-Onge, M., Simm, C., Stansfield, B.L., Veilleux, G., Whyte, D., and Zuzak, W.

Published
1989
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