Overview of the EAST in-vessel components upgrade

Overview of the EAST in-vessel components upgrade
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DOI:
10.1016/j.fusengdes.2015.06.084
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发表时间:
2015-10
影响因子:
1.7
通讯作者:
D. Yao;G. Luo;S. Du;Lei Cao;Zibo Zhou;T. Xu;X. Ji;Changle Liu;Chao Liang;Qiang Li
D. Yao;G. Luo;S. Du;Lei Cao;Zibo Zhou;T. Xu;X. Ji;Changle Liu;Chao Liang;Qiang Li
中科院分区:
工程技术3区
文献类型:
--
作者:
D. Yao;G. Luo;S. Du;Lei Cao;Zibo Zhou;T. Xu;X. Ji;Changle Liu;Chao Liang;Qiang Li

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2011年,EAST超导托卡马克的容器组件从全碳等离子体表面材料(PFM)升级为上下导流器的碳PFM,其他表面的钼PFM。碳瓦机械连接到CuCrZr散热器可以处理热流通量~ 3 MW/m2。EAST计划将等离子加热功率升级到36兆瓦。在此之后,用于稳态运行的转化器的热通量将达到10mw /m2,用于瞬态运行的热通量将达到15mw /m2。升级转向器以适应高性能等离子体操作要求是必要的。为处理高热流密度的EAST上导流器,研制了具有类似iter的单块和扁平钨工艺的钨PFM。为满足钨导流器泵送的要求,设计了一种安装在导流器上部的低温泵。2012年在EAST等离子体操作中观测到i型边缘局域模式(ELM)。为了缓解ELM,开发了与ITER类似的容器线圈绝缘技术的共振磁扰动线圈。垂直稳定(VS)控制线圈也升级为类似iter的绝缘技术,并且优化了线圈的位置,以获得更有效的不稳定控制。
In-vessel components of the EAST superconducting tokamak upgraded from full carbon plasma facing material (PFM) to carbon PFM for upper and lower divertor, and molybdenum PFM for other surface in 2011. Carbon tiles were mechanical connected to CuCrZr heat sink can handle heat flux ∼3 MW/m2. EAST was planned to update plasma heating power to 36 MW. After that heat flux to divertor will be up to 10 MW/m2for steady state operation and 15 MW/m2for transient. Upgrading divertor accommodate high performance plasma operation requirement is necessary. Tungsten PFM with ITER-like monoblock and flat tungsten technology was developed for EAST upper divertor to handle the high heat flux. To meet tungsten divertor pumping requirement an in-vessel cryo-pump was designed to install in upper divertor area.Type-I edge localized mode (ELM) was observed during EAST plasma operation in 2012. Resonant Magnetic Perturbation (RMP) coils with ITER in vessel coils like insulation technology were developed for the ELM mitigation. Vertical Stability (VS) control coils are also upgrade to ITER-like insulation technology, and coils locations were optimized to obtain more effective instability control.