COREDIV modelling of JET ILW discharges with different impurity seeding: nitrogen, neon, argon and krypton

• Autorzy: Ivanova-Stanik I. , Zagórski R.

Identyfikatory

DOI

10.1515/nuka-2017-0001

• Języki publikacji: EN

Abstrakty

EN

Numerical simulations with the COREDIV code of JET H-mode discharges with 25 MW of auxiliary heating in the ITER-like wall (ILW) configuration with different impurity seedings – nitrogen (N), neon (Ne), argon (Ar) and krypton (Kr) – are presented. All simulations have been performed with the same transport model and input discharge parameters like auxiliary heating, volume average plasma density, confi nement factor. Only the seeded impurity puff rate was changed in the calculations. It appears that for the considered heating power of 25 MW and relatively low volume electron average density = 6.2 × 1019 m–3, impurity seeding is necessary. It has been found that for every gas at the maximum level of the seeding rate, allowed by the code convergence, the power to the plate is reduced up to 2–4 MW, with electron temperature at the plate of about 2 eV, indicating semi-detached conditions in the divertor region. It should be noted, however, that in cases with low and medium Z impurity (N, Ne and Ar), tungsten radiation is a signifi cant part of radiation losses and stays above 22–32% of the total energy losses, but for high Z impurity (Kr) it is reduced up to 10% of the total losses. The maximum of the Kr radiation is between the pedestal region and separatrix, showing that radiative mantle can be created, which might have a strong influence on the plasma parameters in the pedestal region.

Słowa kluczowe

EN

impurity seeding; integrated modelling; tokamak

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2017
• Tom: Vol. 62, No. 1
• Strony: 3--7
• Opis fizyczny: Bibliogr. 10 poz., rys.

Twórcy

autor

Ivanova-Stanik I.

• Institute of Plasma Physics and Laser Microfusion, 23 Hery Str., 01-497 Warsaw, Poland, Tel.: [phone], Fax: [phone]

autor

Zagórski R.

• Institute of Plasma Physics and Laser Microfusion, 23 Hery Str., 01-497 Warsaw, Poland, Tel.: [phone], Fax: [phone]

Bibliografia

• 1. Baranov, Yu. F., Challis, C. D., Hobirk, J., Baruzzo, M., mHender, T., & EFDA JET contributors. (2013). Interplay between confinement, impurities and MHD in JET hybrid pulses with ITER like wall. (40th EPS Conference on Plasma Physics, 1–5 July 2013, Espoo, Finland).Europhys. Conf. Abstracts, 37D, P5.142 (4 pp.).
• 2. Wischmeier, M. (2015). High density operation for reactor-relevant power exhaust. J. Nucl. Mater., 463, 22–29.
• 3. Zagorski, R., Telesca, G., Arnoux, G., Beurskens, M., Fundamenski, W., McCormick, K., & JET-EFDA contributors. (2009). Self-consistent modeling of impurity seeded JET advanced tokamak scenarios. J. Nucl. Mater., 390/391, 404–409.
• 4. Ivanova-Stanik, I., Zagórski, R., Telesca, G., Czarnecka, A., Challis, C., Hobirk, J., & JET EFDA contributors. (2014). Integrated modelling of nitrogen seeded JET ILW discharges for H-mode and hybrid scenarios. Contrib. Plasma Phys., 54(4/6), 442–447.DOI: 10.1002/ctpp.201410024.
• 5. Telesca, G., Ivanova-Stanik, I., Zagórski, R., Brezinsek, S., Czarnecka, A., Drewelow, P., Giroud, C., Huber, A., Wiesen, S., Wischmeier, M., & JET contributors. (2015). Numerical simulations of JET discharges with the ITER-like wall for different nitrogen seeding scenarios. J. Nucl. Mater., 463, 577–581.http://dx.doi.org/10.1016/j.jnucmat.2014.11.024.
• 6. Zagórski, R., Ivanova-Stanik, I., Czarnecka, A., Telesca, G., Brezinsek, S., & JET EFDA contributors. (2015). Infl uence of seeding and SOL transport on plasma parameters in JET ITER-like wall H-mode discharges. J. Nucl. Mater., 463, 649–653. http://dx.doi.org/10.1016/j.jnucmat.2014.11.024.
• 7. ITER. (2013, January 7). ITER Physics Guidelines ITER Report. (ITER N 19 FDR 101-07-13 R 0.1). Available from https://fusion.gat.com/iter/iter-fdr/final-report-sep-2001/Dsgn_Basis_Documents_(DBDs)/Phys_Guidelines.pdf.
• 8. Zagorski, R., Ivanova-Stanik, R. I., & Stankiewicz, R. (2013). Simulations with the COREDIV code of DEMO discharges. Nucl. Fusion, 53(7), 073030(6 pp.).
• 9. Ivanova-Stanik, I., & Zagorski, R. (2015). Mitigation of the divertor heat load in DEMO reactor by impurity seeding. J. Nucl. Mater., 463, 596–600.
• 10. Martin, Y. R., Takizuka, T., & ITPA CDBM H-mode Threshold Database Working Group. (2008). Power requirement for accessing the H-mode in ITER. J. Phys.-Conf. Series, 123(1), 012033. DOI: 10.1088/1742-6596/123/1/012033.

Uwagi

PL

Opracowanie ze środków MNiSW w ramach umowy 812/P-DUN/2016 na działalność upowszechniającą naukę (zadania 2017).