Poloidal field system and advanced divertor equilibrium configuration design of the EHL-2 spherical torus

被引：0

作者：

顾翔 ^{[1
,2
]}

尹刚 ^{[1
,2
]}

石跃江 ^{[1
,2
]}

董力立 ^{[1
,2
]}

王宇 ^{[1
,2
]}

臧红 ^{[1
,2
]}

杨圆明 ^{[1
,2
]}

谢华生 ^{[1
,2
]}

董家齐 ^{[1
,3
]}

彭元凯 ^{[1
,2
]}

袁保山 ^{[1
,2
]}

杨青巍 ^{[3
]}

梁云峰 ^{[1
,4
]}

宋显明 ^{[1
,2
]}

刘敏胜 ^{[1
,2
]}

the EHL Team ^{[2
,1
,2
]}

机构：

[1] Hebei Key Laboratory of Compact Fusion

[2] ENN Science and Technology Development Co, Ltd

[3] Southwestern Institute of Physics

[4] Forschungszentrum Jülich GmbH, Institute of Fusion Energy and Nuclear Waste

来源：

Plasma Science and Technology | 2025年 / 27卷 / 02期

关键词：

D O I：

暂无

中图分类号：

TL631.24 [];

学科分类号：

摘要：

The EHL-2（ENN He-Long 2） spherical torus（ST） project focuses on advancing spherical torus technology to address the unique challenges of p-11B fusion,which demands significantly higher ion temperature and heat flux to the divertor plate compared to traditional deuterium-tritium fusion.With a major radius of 1.05 m and a plasma current of 3 MA,the project aims to evaluate and optimize advanced divertor configurations,specifically the Super-X and X-point target（XPT）divertors.The design incorporates an up-down double-null configuration featuring a conventional inner divertor and an XPT outer divertor to effectively reduce the heat flux.The poloidal field（PF） coil system is meticulously optimized to balance engineering constraints with the flexibility in equilibrium configurations.This design is expected to provide a reference equilibrium configuration for other physics design issues and offer critical insight into heat load management.

引用

页码：125 / 133

页数：9

共 35 条

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