Design study of ITER-like divertor target for DEMO

Design study of ITER-like divertor target for DEMO
复制标题

DOI:
10.1016/j.fusengdes.2015.02.056
复制
发表时间:
2015-10
影响因子:
1.7
通讯作者:
F. Crescenzi;C. Bachmann;M. Richou;S. Roccella;E. Visca;J. You
F. Crescenzi;C. Bachmann;M. Richou;S. Roccella;E. Visca;J. You
中科院分区:
工程技术3区
文献类型:
--
作者:
F. Crescenzi;C. Bachmann;M. Richou;S. Roccella;E. Visca;J. You

文献摘要

被引文献

相似文献

近期水冷目标解决方案必须与所需的技术及其在“演示”条件下的功率排放限制一起进行评估。基于单块技术的类ITER设计概念,采用W作为装甲材料,CuCrZr-IG作为结构材料,中间层为纯铜,也是DEMO的一个很有前途的解决方案。这项工作报告了一个“优化”的类ITER水冷转向器的设计研究,该转向器能够承受DEMO运行条件所要求的10 MW m−2的热通量。面向等离子体单元(PFU)的优化旨在通过改变一些几何参数(整体尺寸、夹层厚度以及管直径和厚度)来增强部件的热机械行为。采用有限元分析软件ANSYS,采用多变量优化算法进行优化。为简单起见,冷却剂液压条件(入口压力、温度和速度)是固定的。本研究以弹性分析与三维模拟为基础,并以ITER SDC-IC标准与低周疲劳(LCF)为依据,评估最佳几何形状。还估计了临界热通量(CHF)的裕度。下一步的工作计划预计将进行进一步的设计研究(考虑到中子辐射对材料性能的影响)以及实体模型制造和高热通量(HHF)测试。
A near-term water-cooled target solution has to be evaluated together with the required technologies and its power exhaust limit under ‘DEMO’ conditions. The ITER-like design concept based on the mono-block technology using W as armour material and the CuCrZr-IG as structural material with an interlayer of pure copper represents a promising solution also for DEMO.This work reports the design study of an “optimized” ITER-like Water Cooled Divertor able to withstand a heat flux of 10 MW m−2, as requested for DEMO operating conditions. The optimization of plasma facing unit (PFU) aims to enhance the thermo-mechanical behaviour of the component by varying some geometrical parameters (monoblock size, interlayer thickness and, tube diameter and thickness). The optimization was performed by means of the multi-variable optimization algorithms using the FEM code ANSYS. The coolant hydraulic conditions (inlet pressure, temperature and velocity) were fixed for simplicity. This study is based on elastic analysis and 3 dimensional modelling.The resulting optimized geometry was evaluated on the basis of the ITER SDC-IC criteria and in terms of low cycle fatigue (LCF). The margin to the critical heat flux (CHF) was also estimated.Further design study (taking into account the effect of neutron radiation on the material properties) together with mock-up fabrication and high-heat-flux (HHF) tests are foreseen in next work programmes.