Numerical Study of High Heat Flux Performances of Flat-Tile Divertor Mock-ups with Hypervapotron Cooling Concept  

作　　者：陈蕾 刘翔 练友运 才来中 

机构地区：[1]Southwestern Institute of Physics

出　　处：《Plasma Science and Technology》2015年第9期792-796,共5页等离子体科学和技术（英文版）

基　　金：supported by the National Magnetic Confinement Fusion Science Program of China(Nos.2011GB110001 and 2011GB110004)

摘　　要：The hypervapotron（HV）,as an enhanced heat transfer technique,will be used for ITER divertor components in the dome region as well as the enhanced heat flux first wall panels.W-Cu brazing technology has been developed at SWIP（Southwestern Institute of Physics）,and one W/CuCrZr/316 LN component of 450 mm×52 mm×166 mm with HV cooling channels will be fabricated for high heat flux（HHF） tests.Before that a relevant analysis was carried out to optimize the structure of divertor component elements.ANSYS-CFX was used in CFD analysis and ABAQUS was adopted for thermal-mechanical calculations.Commercial code FE-SAFE was adopted to compute the fatigue life of the component.The tile size,thickness of tungsten tiles and the slit width among tungsten tiles were optimized and its HHF performances under International Thermonuclear Experimental Reactor（ITER） loading conditions were simulated.One brand new tokamak HL-2M with advanced divertor configuration is under construction in SWIP,where ITER-like flat-tile divertor components are adopted.This optimized design is expected to supply valuable data for HL-2M tokamak.The hypervapotron（HV）,as an enhanced heat transfer technique,will be used for ITER divertor components in the dome region as well as the enhanced heat flux first wall panels.W-Cu brazing technology has been developed at SWIP（Southwestern Institute of Physics）,and one W/CuCrZr/316 LN component of 450 mm×52 mm×166 mm with HV cooling channels will be fabricated for high heat flux（HHF） tests.Before that a relevant analysis was carried out to optimize the structure of divertor component elements.ANSYS-CFX was used in CFD analysis and ABAQUS was adopted for thermal-mechanical calculations.Commercial code FE-SAFE was adopted to compute the fatigue life of the component.The tile size,thickness of tungsten tiles and the slit width among tungsten tiles were optimized and its HHF performances under International Thermonuclear Experimental Reactor（ITER） loading conditions were simulated.One brand new tokamak HL-2M with advanced divertor configuration is under construction in SWIP,where ITER-like flat-tile divertor components are adopted.This optimized design is expected to supply valuable data for HL-2M tokamak.

关 键 词：divertor components hypervapotron cooling channels heat transfer fatigue life 

分 类 号：TL631.24[核科学技术—核技术及应用] TN830.5[电子电信—信息与通信工程]