当前位置: X-MOL 学术Phys. Atomic Nucl. › 论文详情
Our official English website, www.x-mol.net, welcomes your feedback! (Note: you will need to create a separate account there.)
New Version of the KTM Lithium Divertor
Physics of Atomic Nuclei ( IF 0.4 ) Pub Date : 2021-02-11 , DOI: 10.1134/s1063778820070121
A. V. Vertkov , M. Yu. Zharkov , I. E. Lyublinski , A. V. Berlov , I. L. Tazhibayeva , Yu. V. Ponkratov , Yu. N. Gordienko

Abstract

At present, the Kazakhstan Tokamak for Material testing (KTM) project is in progress. The optimization of innovative design elements of the divertor is carried out at the KTM, in addition to studying materials applied for fusion technologies. The design of the lithium divertor module based on lithium capillary porous systems has been developed and tested successfully in real tokamak conditions. In this design, the problem of removing high-density heat flows is solved by using liquid metal coolant based on the Na–K eutectic alloy. The requirements for the improved safety and the divertor design compatibility with other in-vessel water-cooled elements of the tokamak and temperature limitation of the receiving lithium surface to the level <600°C at the heat flows of 10–20 MW/m2 stipulated a new design solution of the divertor experimental module and the use of a totally new coolant—water flow dispersed with gas (gas-water spray). In the paper, the design solutions of the new version of the module, the coolant parameters, and the cooling system layout are described and substantiated. The experimental results on determining the heat transfer coefficient of the coolant based on gas-water spray are considered.



中文翻译:

新版KTM锂分流器

摘要

目前,哈萨克斯坦托卡马克材料测试(KTM)项目正在进行中。除了研究用于融合技术的材料外,KTM还对分流器的创新设计元素进行了优化。基于锂毛细管多孔系统的锂分流器模块的设计已经开发并在实际的托卡马克条件下成功进行了测试。在此设计中,通过使用基于Na-K共晶合金的液态金属冷却剂解决了消除高密度热流的问题。更高的安全性要求以及与托卡马克的其他船上水冷元件的分流器设计兼容性以及在10-20 MW / m 2的热流下接收锂表面的温度限制在<600°C的水平规定了偏滤器实验模块的新设计解决方案,并使用了全新的冷却剂-气体分散的水流(气-水喷雾)。在本文中,描述并证实了新版本模块的设计解决方案,冷却液参数和冷却系统布局。考虑了基于气-水喷雾确定冷却剂传热系数的实验结果。

更新日期:2021-02-11
down
wechat
bug