Power conversion from spherical tokamak test reactor with helium-cooled and water-cooled blanket

被引:4
作者
Prajapati, Piyush [1 ,2 ]
Deshpande, Shishir [1 ,2 ]
机构
[1] Inst Plasma Res, Gandhinagar 382428, India
[2] Homi Bhabha Natl Inst, Mumbai 400094, Maharashtra, India
关键词
Power extraction; Energy storage system; Steam generator (SG); Power conversion cycles; SUPERCRITICAL CARBON-DIOXIDE; NUCLEAR-SCIENCE FACILITY; SECONDARY CIRCUIT; FUSION; PLANT; DESIGN; ENERGY; PERFORMANCE; CYCLES; SYSTEMS;
D O I
10.1016/j.fusengdes.2022.113024
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
Possible configurations for Power Conversion System (PCS) for a futuristic, small, pulsed Spherical Tokamak (ST) fusion reactor are presented. For the typical blanket coolant choices namely, helium and water, an intermediate heat-exchanger (IHX) cum buffer energy storage system (ESS) with Molten Salt (MS) is introduced to examine Rankine and Brayton cycle's effectiveness. Preliminary thermal sizing of the involved heat-exchangers and pa-rameters of the optimized cycle are discussed. S-CO2 Brayton cycle seems to be a promising candidate for effi-cient power conversion for a pulsed plasma reactor with efficiency of 42.75%. Rankine cycle yields efficiency of 35-42% depending on water/helium as the choice of the blanket coolant.
引用
收藏
页数:11
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