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Title: First ERO2.0 modeling of Be erosion and non-local transport in JET ITER-like wall

Authors:
 [1];  [2];  [2];  [1];  [3];  [3];  [3];  [4];  [1];  [3];  [5];  [6];  [7];  [2];  [2]; ORCiD logo [8]
  1. Forschungszentrum Julich, Germany
  2. Forschungszentrum Julich GmbH, Institut fur Energie-und Klimaforschung-Plasmaphysik (IEK-4), Germany
  3. Forschungszentrum Jülich GmbH, Institute for Advanced Simulation, Jülich Supercomputing 8 9 Centre
  4. EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, UK
  5. French Atomic Energy Commission (CEA), Institute for Magnetic Fusion Research (IRFM)
  6. National Research Nuclear University (MEPhI), Moscow, Russia
  7. CEA IRFM, St. Paul-lez-Durance, France
  8. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1407755
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications - Neuss/Düsseldorf, , Germany - 5/16/2017 8:00:00 AM-5/19/2017 8:00:00 AM
Country of Publication:
United States
Language:
English

Citation Formats

Kirschner, A., Romazanov, J., Borodin, D., Huber, A., Steinbusch, B., Brommel, D., Linsmeier, Ch., Silburn, S., Brezinsek, S., Gibbon, P., Firdaouss, M., Eksaeva, A., Bufferand, H., Huber, V, Borodkina, I., and Lasa Esquisabel, Ane. First ERO2.0 modeling of Be erosion and non-local transport in JET ITER-like wall. United States: N. p., 2017. Web.
Kirschner, A., Romazanov, J., Borodin, D., Huber, A., Steinbusch, B., Brommel, D., Linsmeier, Ch., Silburn, S., Brezinsek, S., Gibbon, P., Firdaouss, M., Eksaeva, A., Bufferand, H., Huber, V, Borodkina, I., & Lasa Esquisabel, Ane. First ERO2.0 modeling of Be erosion and non-local transport in JET ITER-like wall. United States.
Kirschner, A., Romazanov, J., Borodin, D., Huber, A., Steinbusch, B., Brommel, D., Linsmeier, Ch., Silburn, S., Brezinsek, S., Gibbon, P., Firdaouss, M., Eksaeva, A., Bufferand, H., Huber, V, Borodkina, I., and Lasa Esquisabel, Ane. 2017. "First ERO2.0 modeling of Be erosion and non-local transport in JET ITER-like wall". United States. doi:. https://www.osti.gov/servlets/purl/1407755.
@article{osti_1407755,
title = {First ERO2.0 modeling of Be erosion and non-local transport in JET ITER-like wall},
author = {Kirschner, A. and Romazanov, J. and Borodin, D. and Huber, A. and Steinbusch, B. and Brommel, D. and Linsmeier, Ch. and Silburn, S. and Brezinsek, S. and Gibbon, P. and Firdaouss, M. and Eksaeva, A. and Bufferand, H. and Huber, V and Borodkina, I. and Lasa Esquisabel, Ane},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2017,
month =
}

Conference:
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  • No abstract prepared.
  • Sputtering erosion/redeposition is analyzed for IAEA [Report GA10FDR1-01-07-13 (2001)] plasma facing components, with scrape-off layer (SOL) plasma convective radial transport and nonconvective (diffusion-only) transport. The analysis uses the UEDGE code [T .D. Rognlien et al., J. Nucl. Mater. 196, 347 (1992)] and DEGAS code [D. P. Stotler et al., Contrib. Plasma Phys. 40, 221 (2000) ] to compute plasma SOL profiles and ion and neutral fluxes to the wall, TRIM-SP code [J. P. Biersack, W. Eckstein, J. Appl. Phys. A34, 73 (1984)] to compute sputter yields, and the REDEP/WBC code package [J. N. Brooks, Fusion Eng. Des. 60, 515 (2002)]more » for three-dimensional kinetic modeling of sputtered particle transport. Convective transport is modeled for the background plasma by a radially varying outward-flow component of the fluid velocity, and for the impurity ions by three models designed to bracket existing models/data. Results are reported here for the first wall with the reference beryllium coating and an alternative tungsten coating. The analysis shows: (1) sputtering erosion for convective flow is 20-40 times higher than for diffusion-only but acceptably low ({approx}0.3 nm/s) for beryllium, and very low ({approx}0.002 nm/s) for tungsten; (2) plasma contamination by wall sputtering, with convective flow, is of order 1% for beryllium and negligible for tungsten; (3) wall-to-divertor beryllium transport may be significant ({approx}10%-60% of the sputtered Be current); (4) tritium co-deposition in redeposited beryllium may be high ({approx}1-6 gT/400 s pulse)« less
  • ITER inductive power operation is modeled and simulated using a thermal-hydraulics system code (RELAP5) integrated with a 3-D CFD (SC-Tetra) code. The Primary Heat Transfer System (PHTS) functions are predicted together with the main parameters operational ranges. The control algorithm strategy and derivation are summarized as well. The First Wall and Blanket modules are the primary components of PHTS, used to remove the major part of the thermal heat from the plasma. The modules represent a set of flow channels in solid metal structure that serve to absorb the radiation heat and nuclear heating from the fusion reactions and tomore » provide shield for the vacuum vessel. The blanket modules are water cooled. The cooling is forced convective with constant blanket inlet temperature and mass flow rate. Three independent water loops supply coolant to the three blanket sectors. The main equipment of each loop consists of a pump, a steam pressurizer and a heat exchanger. A major feature of ITER is the pulsed operation. The plasma does not burn continuously, but on intervals with large periods of no power between them. This specific feature causes design challenges to accommodate the thermal expansion of the coolant during the pulse period and requires active temperature control to maintain a constant blanket inlet temperature.« less