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

来源：

FUSION ENGINEERING AND DESIGN | 2022年 / 176卷

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

页数：11

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