Numerical study and experimental validation of heat transfer capacity of flat-type divertor for fusion reactor

被引:1
|
作者
Mou, Nanyu [1 ]
Lu, Mingxiang [2 ]
Feng, Mingchi [1 ]
Huang, Shuai [1 ]
Han, Le [3 ]
Yao, Damao [3 ]
机构
[1] Chongqing Univ Posts & Telecommun, Sch Adv Mfg Engn, Chongqing 400065, Peoples R China
[2] Nanjing Univ Sci & Technol, Sch Energy & Power Engn, MIIT Key Lab Thermal Control Elect Equipment, Nanjing 210094, Peoples R China
[3] Chinese Acad Sci, Hefei Inst Phys Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
关键词
Divertor; Fusion reactor; Flat-type; Advanced material; Heat transfer capacity; TUNGSTEN; ITER;
D O I
10.1016/j.nme.2024.101716
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The divertor must simultaneously withstand unprecedented high heat fluxes of up to 20 MW/m2 and high-energy neutron irradiation of 14-MeV during fusion reactor operation. Accordingly, it is necessary to simultaneously meet the excellent heat dissipation capacity of the divertor and maintain good material performance in harsh neutron irradiation environments. The flat-type divertor demonstrates better heat transfer performance compared to monoblock divertor. Nevertheless, under the condition of a heat flux of 20 MW/m2, the heat transfer and thermal fatigue performance of flat-type divertor using advanced materials are still unidentified. In this study, we conducted a thorough analysis of the heat transfer capabilities and thermal fatigue characteristics of potassium-doped tungsten (KW)/Cu/Oxide dispersion strengthened copper (ODS-Cu)/reduced activation ferritic/martensitic (RAFM) divertor mockup adopts hypervaportron (HV) structure by numerical simulations combined with experiments. The numerical results indicate that the flat-type KW/Cu/ODS-Cu/RAFM divertor mockup expresses excellent heat transfer capacity. The contact area between the edge of the fins and the bottom surface of the ODS-Cu heat sink induces a significant increase in water flow velocity to 15 m/s. The peak temperature of loaded KW surface is only 985 degrees C under the flow rate of 5 t/h and inlet temperature of 20 degrees C. During the high heat flux tests, the prepared flat-type divertor mockup successful endured 1000 cycles of 20 MW/m2 with the peak temperature of 883 degrees C, and the surface temperature experienced a fluctuation of 2.4 % during the thermal fatigue tests. This study can provide a strong data reference and technical support for the development of fusion reactors, and is of great significance in advancing the commercialization of fusion energy.
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页数:8
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