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Surface heat loads on the ITER divertor vertical targets
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SYSNO ASEP 0477431 Druh ASEP J - Článek v odborném periodiku Zařazení RIV J - Článek v odborném periodiku Poddruh J Článek ve WOS Název Surface heat loads on the ITER divertor vertical targets Tvůrce(i) Gunn, J. P. (FR)
Carpentier-Chouchana, S. (FR)
Escourbiac, F. (FR)
Hirai, T. (FR)
Panayotis, S. (FR)
Pitts, R.A. (FR)
Corre, Y. (FR)
Dejarnac, Renaud (UFP-V) RID, ORCID
Firdaouss, M. (FR)
Kočan, M. (FR)
Komm, Michael (UFP-V) RID, ORCID
Kukushkin, A. (RU)
Languille, P. (FR)
Missirlian, M. (FR)
Zhao, W. (CN)
Zhong, G. (CN)Číslo článku 046025 Zdroj.dok. Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
Roč. 57, č. 4 (2017)Poč.str. 35 s. Forma vydání Tištěná - P Jazyk dok. eng - angličtina Země vyd. AT - Rakousko Klíč. slova ITER ; divertor ; ELM heat load ; inter-ELM heat load ; tungsten Vědní obor RIV BL - Fyzika plazmatu a výboje v plynech Obor OECD Fluids and plasma physics (including surface physics) Institucionální podpora UFP-V - RVO:61389021 UT WOS 000405944300012 EID SCOPUS 85015768044 DOI 10.1088/1741-4326/aa5e2a Anotace The heating of tungsten monoblocks at the ITER divertor vertical targets is calculated using the heat flux predicted by three-dimensional ion orbit modelling. The monoblocks are beveled to a depth of 0.5 mm in the toroidal direction to provide magnetic shadowing of the poloidal leading edges within the range of specified assembly tolerances, but this increases the magnetic field incidence angle resulting in a reduction of toroidal wetted fraction and concentration of the local heat flux to the unshadowed surfaces. This shaping solution
successfully protects the leading edges from inter-ELM heat loads, but at the expense of (1) temperatures on the main loaded surface that could exceed the tungsten recrystallization temperature in the nominal partially detached regime, and (2) melting and loss of margin against critical heat flux during transient loss of detachment control. During ELMs, the risk of monoblock edge melting is found to be greater than the risk of full surface melting on the plasma-wetted zone. Full surface and edge melting will be triggered by uncontrolled ELMs
in the burning plasma phase of ITER operation if current models of the likely ELM ion impact energies at the divertor targets are correct. During uncontrolled ELMs in pre-nuclear deuterium or helium plasmas at half the nominal plasma current and magnetic field, full surface melting should be avoided, but edge melting is predicted.Pracoviště Ústav fyziky plazmatu Kontakt Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Rok sběru 2018
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