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TOKES studies of the thermal quench heat load reduction in mitigated ITER disruptions

Pestchanyi, S. 1; Lehnen, M.; Pitts, R. A.; Saibene, G.
1 Karlsruher Institut für Technologie (KIT)


Disruption mitigation by massive gas injection (MGI) of Ne gas has been simulated using the 3D TOKES code that includes the injectors of the Disruption Mitigation System (DMS) as it will be implemented in ITER. The simulations have been done using a quasi-3D approach, which gives an upper limit for the radiation heat load (notwithstanding possible asymmetries in radial heat flux associated with MHD). The heating of the first wall from the radiation flash has been assessed with respect to injection quantity, the number of injectors, and their location for an H-mode ITER discharge with 280 MJ of thermal energy. Simulations for the maximum quantity of Ne (8 kPa m3) have shown that wall melting can be avoided by using solely the three injectors in the upper ports, whereas shallow melting occurred when the midplane injector had been added. With all four injectors, melting had been avoided for a smaller neon quantity of 250 Pa m3 that provides still a sufficient radiation level for thermal load mitigation.

Verlagsausgabe §
DOI: 10.5445/IR/1000076539
Veröffentlicht am 14.11.2017
DOI: 10.1016/j.nme.2016.12.007
Zitationen: 3
Zitationen: 3
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 08.2017
Sprache Englisch
Identifikator ISSN: 2352-1791
KITopen-ID: 1000076539
HGF-Programm 31.03.06 (POF III, LK 01) Brutblanket-Entwicklung
Erschienen in Nuclear materials and energy
Verlag Elsevier
Band 12
Seiten 959–966
Nachgewiesen in Dimensions
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