作者
Jonathan Coburn, M Lehnen, RA Pitts, G Simic, FJ Artola, Emil Thorén, S Ratynskaia, K Ibano, M Brank, L Kos, R Khayrutdinov, VE Lukash, B Stein-Lubrano, E Matveeva, G Pautasso
发表日期
2021/12/20
期刊
Nuclear Fusion
卷号
62
期号
1
页码范围
016001
出版商
IOP Publishing
简介
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 χ. Magnetic field line tracing using SMITER calculates time-dependent, 3D maps of surface power density q⊥ 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 …
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