Physics basis for the first ITER tungsten divertor
Abstract
On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor lifetime constraint. The principal focus is on the main design driver, steady state power fluxes in the DT phases, obtained from simulations using the 2-D SOLPS-4.3 and SOLPS-ITER plasma boundary codes, assuming the use of the low Z seeding impurities nitrogen (N) and neon (Ne). A new perspective on the simulation database is adopted, concentrating purely on the divertor physics aspects rather than on the core-edge integration, which has been studied extensively in the course of the divertor design evolution and is published elsewhere. Emphasis is placed on factors which may increase the peak steady state loads: divertor target shaping for component misalignment protection, the influence of fluid drifts, and the consequences of narrow scrape-off layer heat flux channels. All tend to push the divertor into an operating space at higher sub-divertor neutral pressure in order to remain at power flux densities acceptable for the targetmore »
- Authors:
- Publication Date:
- Research Org.:
- Univ. of Wisconsin, Madison, WI (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC); Russian Science Foundation
- OSTI Identifier:
- 1560688
- Alternate Identifier(s):
- OSTI ID: 1611763
- Grant/Contract Number:
- SC0012315; SC0013911; 17-12-01020
- Resource Type:
- Published Article
- Journal Name:
- Nuclear Materials and Energy
- Additional Journal Information:
- Journal Name: Nuclear Materials and Energy Journal Volume: 20 Journal Issue: C; Journal ID: ISSN 2352-1791
- Publisher:
- Elsevier
- Country of Publication:
- Netherlands
- Language:
- English
- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; nuclear science & technology; ITER; tungsten; divertor; heat fluxes; SOLPS
Citation Formats
Pitts, R. A., Bonnin, X., Escourbiac, F., Frerichs, H., Gunn, J. P., Hirai, T., Kukushkin, A. S., Kaveeva, E., Miller, M. A., Moulton, D., Rozhansky, V., Senichenkov, I., Sytova, E., Schmitz, O., Stangeby, P. C., De Temmerman, G., Veselova, I., and Wiesen, S. Physics basis for the first ITER tungsten divertor. Netherlands: N. p., 2019.
Web. doi:10.1016/j.nme.2019.100696.
Pitts, R. A., Bonnin, X., Escourbiac, F., Frerichs, H., Gunn, J. P., Hirai, T., Kukushkin, A. S., Kaveeva, E., Miller, M. A., Moulton, D., Rozhansky, V., Senichenkov, I., Sytova, E., Schmitz, O., Stangeby, P. C., De Temmerman, G., Veselova, I., & Wiesen, S. Physics basis for the first ITER tungsten divertor. Netherlands. https://doi.org/10.1016/j.nme.2019.100696
Pitts, R. A., Bonnin, X., Escourbiac, F., Frerichs, H., Gunn, J. P., Hirai, T., Kukushkin, A. S., Kaveeva, E., Miller, M. A., Moulton, D., Rozhansky, V., Senichenkov, I., Sytova, E., Schmitz, O., Stangeby, P. C., De Temmerman, G., Veselova, I., and Wiesen, S. Thu .
"Physics basis for the first ITER tungsten divertor". Netherlands. https://doi.org/10.1016/j.nme.2019.100696.
@article{osti_1560688,
title = {Physics basis for the first ITER tungsten divertor},
author = {Pitts, R. A. and Bonnin, X. and Escourbiac, F. and Frerichs, H. and Gunn, J. P. and Hirai, T. and Kukushkin, A. S. and Kaveeva, E. and Miller, M. A. and Moulton, D. and Rozhansky, V. and Senichenkov, I. and Sytova, E. and Schmitz, O. and Stangeby, P. C. and De Temmerman, G. and Veselova, I. and Wiesen, S.},
abstractNote = {On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor lifetime constraint. The principal focus is on the main design driver, steady state power fluxes in the DT phases, obtained from simulations using the 2-D SOLPS-4.3 and SOLPS-ITER plasma boundary codes, assuming the use of the low Z seeding impurities nitrogen (N) and neon (Ne). A new perspective on the simulation database is adopted, concentrating purely on the divertor physics aspects rather than on the core-edge integration, which has been studied extensively in the course of the divertor design evolution and is published elsewhere. Emphasis is placed on factors which may increase the peak steady state loads: divertor target shaping for component misalignment protection, the influence of fluid drifts, and the consequences of narrow scrape-off layer heat flux channels. All tend to push the divertor into an operating space at higher sub-divertor neutral pressure in order to remain at power flux densities acceptable for the target material. However, a revised criterion for the maximum tolerable loads based on avoidance of W recrystallization, sets an upper limit potentially ~50% higher than the previously accepted value of ~10 MW m-2, a consequence both of the choice of material and the finalized component design. Although the simulation database is currently restricted to the 2-D toroidally symmetric situation, considerable progress is now also being made using the EMC3-Eirene 3-D code suite for the assessment of power loading in the presence of magnetic perturbations for ELM control. Some new results for low input power corresponding to the early H-mode operation phases are reported, showing that even if realistic plasma screening is taken into account, significant asymmetric divertor heat fluxes may arise far from the unperturbed strike point. The issue of tolerable limits for transient heat pulses is an open and key question. A new scaling for ELM power deposition has shown that whilst there may be more latitude for operation at higher current without ELM control, the ultimate limit is likely to be set more by material fatigue under large numbers of sub-threshold melting events.},
doi = {10.1016/j.nme.2019.100696},
journal = {Nuclear Materials and Energy},
number = C,
volume = 20,
place = {Netherlands},
year = {Thu Aug 01 00:00:00 EDT 2019},
month = {Thu Aug 01 00:00:00 EDT 2019}
}
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- Li, J.; Guo, H. Y.; Wan, B. N.
- Nature Physics, Vol. 9, Issue 12
Two-point analysis of the numerical modelling of detached divertor plasmas
journal, October 2009
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- Plasma Physics and Controlled Fusion, Vol. 51, Issue 11
Validation of TOKES vapor shield simulations against experiments in the 2MK-200 facility
journal, November 2017
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- Fusion Engineering and Design, Vol. 124
MHD stability of the ITER pedestal and SOL plasma and its influence on the heat flux width
journal, August 2015
- Loarte, A.; Liu, F.; Huijsmans, G. T. A.
- Journal of Nuclear Materials, Vol. 463
Status and physics basis of the ITER divertor
journal, December 2009
- Pitts, R. A.; Kukushkin, A.; Loarte, A.
- Physica Scripta, Vol. T138