Conceptual design of a component test facility based on the spherical tokamak

Conceptual design of a component test facility based on the spherical tokamak
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DOI:
10.1016/j.fusengdes.2008.05.002
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发表时间:
2008-12-01
影响因子:
1.7
通讯作者:
Wilson, H. R.
Wilson, H. R.
中科院分区:
工程技术3区
文献类型:
--
作者:
Voss, G. M.;Davis, S.;Wilson, H. R.

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小型稳态球形托卡马克(ST)为同时产生中子提供了一个有吸引力的系统。在所需的聚变发电厂条件下,有效测试和优化包层模块、第一壁结构和其他组件所需的颗粒和热通量。该组件测试设施(CTF)将补充和扩展IFMIF对材料的鉴定,并可以与演示一起操作,从而在商业聚变动力发展的这个关键阶段减少延迟风险,并扩大选择范围。ST-CTF具有许多优点,包括低氚消耗、易于维护和紧凑的组装,并将在Q类似于1的强驱动模式下运行。当前的驱动将由自举电流和中性束注入系统的混合提供。测试中的毯子模块使用折叠式系统拆卸和更换,整个中柱组件可以通过托卡马克组件下方的液压提升系统轻松拆卸。单圈环形磁场线圈具有水冷铜中心杆和多个返回支路,这需要低电压、大电流的电源。极向场线圈也是水冷的,但使用了玻璃纤维增强的氰酸酯树脂绝缘,与传统的环氧树脂系统相比,提供了更高的抗辐射能力和更高的工作温度。当工作在L模式时,大部分的排气功率被导向双零偏滤器结构的外腿,在那里产生了高功率密度和高材料烧蚀率。一种基于级联鹅卵石流动的新型偏滤器靶标是为这一应用开发的一种选择。皇冠版权所有(C)2008由爱思唯尔出版。保留所有权利。
A small steady state spherical tokamak (ST) offers an attractive system for producing simultaneously the neutron. particle and heat fluxes necessary to effectively test and optimise blanket modules, first wall structures and other components under the required fusion power plant conditions. This component test facility (CTF) would complement and extend the qualification of materials by IFMIF and could operate in association with DEMO thus reducing the risk of delays, and extending the options, during this crucial stage of the development of commercial fusion power.The ST-CTF offers many advantages including low tritium consumption, ease of maintenance and a compact assembly and would operate in a strongly driven mode in which Q similar to 1. The current drive would be provided by a mix of bootstrap current and neutral beam injection systems. The blanket modules under test are removed and replaced using a casking system and the entire centre column assembly can be relatively easily removed via a hydraulic lift system beneath the tokamak assembly. The single turn toroidal field coil has a water-cooled copper centre rod with multiple return limbs, which requires a low voltage, high current power supply. The poloidal field coils are also water-cooled but use a glass fibre reinforced cyanate ester resin insulation that offers higher radiation resistance and higher operating temperatures than the conventional epoxy resin systems. When operated in L-mode most of the exhaust power is directed to the outer legs of the double null divertor configuration where high power densities and high material erosion rates are developed. A novel divertor target based on the use of a cascading flow of pebbles is one option being developed for this application. Crown Copyright (C) 2008 Published by Elsevier B.V. All rights reserved.