This title appears in the Scientific Report :
2019
Please use the identifier:
http://hdl.handle.net/2128/22156 in citations.
Please use the identifier: http://dx.doi.org/10.1016/j.nme.2019.01.015 in citations.
Beryllium global erosion and deposition at JET-ILW simulated with ERO2.0
Beryllium global erosion and deposition at JET-ILW simulated with ERO2.0
The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with the ITER-like wall (ILW). The global beryllium (Be) erosion and deposition is simulated and compared to experimental results from passive spectroscopy. For the limiter configurat...
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Personal Name(s): | Romazanov, J. (Corresponding author) |
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Brezinsek, S. / Borodin, D. / Groth, M. / Wiesen, S. / Kirschner, A. / Huber, Alexander / Widdowson, A. / Airila, M. / Eksaeva, A. / Borodkina, I. / Linsmeier, Ch. | |
Contributing Institute: |
JARA - HPC; JARA-HPC Plasmaphysik; IEK-4 |
Published in: | Nuclear materials and energy, 18 (2019) S. 331 - 338 |
Imprint: |
Amsterdam [u.a.]
Elsevier
2019
|
DOI: |
10.1016/j.nme.2019.01.015 |
Document Type: |
Journal Article |
Research Program: |
3D Monte-Carlo simulations of plasma-wall interaction and impurity transport in fusion devices Plasma-Wall-Interaction |
Link: |
OpenAccess OpenAccess |
Publikationsportal JuSER |
Please use the identifier: http://dx.doi.org/10.1016/j.nme.2019.01.015 in citations.
The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with the ITER-like wall (ILW). The global beryllium (Be) erosion and deposition is simulated and compared to experimental results from passive spectroscopy. For the limiter configuration, it is demonstrated that Be self-sputtering is an important contributor (at least 35%) to the Be erosion. Taking this contribution into account, the ERO2.0 modelling confirms previous evidence that high deuterium (D) surface concentrations of up to ∼ 50% atomic fraction provide a reasonable estimate of Be erosion in plasma-wetted areas. For the divertor configuration, it is shown that drifts can have a high impact on the scrape-off layer plasma flows, which in turn affect global Be transport by entrainment and lead to increased migration into the inner divertor. The modelling of the effective erosion yield for different operational phases (ohmic, L- and H-mode) agrees with experimental values within a factor of two, and confirms that the effective erosion yield decreases with increasing heating power and confinement. |