Počet záznamů: 1
Energy deposition and melt deformation on the ITER first wall due to disruptions and vertical displacement events
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SYSNO ASEP 0553538 Druh ASEP J - Článek v odborném periodiku Zařazení RIV J - Článek v odborném periodiku Poddruh J Článek ve WOS Název Energy deposition and melt deformation on the ITER first wall due to disruptions and vertical displacement events Tvůrce(i) Coburn, C. T. (US)
Lehnen, M. (FR)
Pitts, R. (FR)
Simic, G. (FR)
Artola, F. J. (FR)
Thorén, E. (SE)
Ratynskaia, S. (SE)
Ibanoglu, C. (TR)
Brank, M. (SI)
Kos, L. (SI)
Khayrutdinov, R. (RU)
Lukash, V. (RU)
Stein-Lubrano, B. (US)
Matveeva, Ekaterina (UFP-V)
Pautasso, G. (DE)Celkový počet autorů 15 Číslo článku 016001 Zdroj.dok. Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
Roč. 62, č. 1 (2022)Poč.str. 12 s. Jazyk dok. eng - angličtina Země vyd. AT - Rakousko Klíč. slova halo currents ; plasma disruptions ; plasma facing components ; heat loads ; material erosion ; iter Vědní obor RIV BL - Fyzika plazmatu a výboje v plynech Obor OECD Fluids and plasma physics (including surface physics) CEP 8D15001 GA MŠMT - Ministerstvo školství, mládeže a tělovýchovy LM2018117 GA MŠMT - Ministerstvo školství, mládeže a tělovýchovy Způsob publikování Open access Institucionální podpora UFP-V - RVO:61389021 UT WOS 000734359400001 EID SCOPUS 85122629060 DOI 10.1088/1741-4326/ac38c7 Anotace An analysis workflow has been developed to assess energy deposition and material damage for ITER vertical displacement events (VDEs) and major disruptions (MD). This paper describes the use of this workflow to assess the melt damage to be expected during unmitigated current quench (CQ) phases of VDEs and MDs at different points in the ITER research plan. The plasma scenarios are modeled using the DINA code with variations in plasma current I (p), disruption direction (upwards or downwards), Be impurity density n (Be), and diffusion coefficient chi. Magnetic field line tracing using SMITER calculates time-dependent, 3D maps of surface power density q (perpendicular to) on the Be-armored first wall panels (FWPs) throughout the CQ. MEMOS-U determines the temperature response, macroscopic melt motion, and final surface topology of each FWP. Effects of Be vapor shielding are included. Scenarios at the baseline combination of I (p) and toroidal field (15 MA/5.3 T) show the most extreme melt damage, with the assumed n (Be) having a strong impact on the disruption duration, peak q (perpendicular to) and total energy deposition to the first wall. The worst-cases are upward 15 MA VDEs and MDs at lower values of n (Be), with q (perpendicular to,max) = 307 MW m(-2) and maximum erosion losses of similar to 2 mm after timespans of similar to 400-500 ms. All scenarios at 5 MA avoided melt damage, and only one 7.5 MA scenario yields a notable erosion depth of 0.25 mm. These results imply that disruptions during 5 MA, and some 7.5 MA, operating scenarios will be acceptable during the pre-fusion power operation phases of ITER. Preliminary analysis shows that localized melt damage for the worst-case disruption should have a limited impact on subsequent stationary power handling capability. Pracoviště Ústav fyziky plazmatu Kontakt Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Rok sběru 2023 Elektronická adresa https://iopscience.iop.org/article/10.1088/1741-4326/ac38c7
Počet záznamů: 1