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A bulk tungsten tile for JET: Heat flux tests in the MARION facility on the power-handling performance and validation of the thermal model

机译:用于JET的大块钨砖:MARION设施中的热通量测试,涉及功率处理性能和热模型验证

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摘要

In the frame of the ITER-like Wall (ILW) for the JET tokamak, a divertor row made of bulk tungsten material has been developed for the position where the outer strike point is located in most of the foreseen plasma configurations. In the absence of active cooling, this represents a formidable challenge when one considers the temperature reached by tungsten (T_(W.surf)>2000℃) and the vertical gradient ∂T/∂z = 5 × 10~4 K/m. As the development is drawing to an end and most components are in production, actual 1:1 prototypes are exposed to an ion beam with a power density around 7 MW/m~2 on the plasma-facing surface. Advantage is taken of the flexibility of the Marion facility to bombard the tungsten stack under shallow angles of incidence (~6°) with a powerful beam of ions and neutrals (>70 MW/m~2 on axis). The shallow angles are important, with respect to the toroidal wetted surface, for properly simulating the expected performance under actual tokamak conditions. The Marion tests have been used to validate for a few typical cases the thermal calculations that were steadily developed along with the tungsten tile and, at the same time, to gather information on the actual temperatures of individual components. The latter is an important factor to a finer estimation of the power handling capabilities.
机译:在用于JET托卡马克的ITER式墙(ILW)的框架中,已经开发了一种由块状钨材料制成的分流器排,用于在大多数可预见的等离子配置中外部撞击点位于该位置。在没有主动冷却的情况下,当考虑钨的最高温度(T_(W.surf)> 2000℃)和垂直梯度∂T/∂z= 5×10〜4 K / m时,这是一个巨大的挑战。随着开发工作即将结束,并且大多数组件已投入生产,实际的1:1原型在面对等离子体的表面上暴露于功率密度约为7 MW / m〜2的离子束中。利用Marion设施的灵活性,可以用强大的离子束和中性离子束(轴上> 70 MW / m〜2)在浅入射角(〜6°)下轰击钨堆。相对于环形润湿表面,浅角度对于正确模拟实际托卡马克条件下的预期性能非常重要。 Marion测试已用于验证几种典型情况下与钨砖一起稳定发展的热量计算,并同时收集有关单个组件实际温度的信息。后者是对功率处理能力进行更好估计的重要因素。

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  • 来源
    《Fusion Engineering and Design》 |2011年第11期|p.1801-1804|共4页
  • 作者单位

    JET-EFDA. Culham Science Centre, Abingdon OX14 3DB, UK,IEK-4 (Plasma Physics), Forschungszentrum Juelich, Assoc. EURATOM-FZJ, D-52425Juelich. Germany;

    JET-EFDA. Culham Science Centre, Abingdon OX14 3DB, UK,Culham Centre for Fusion Energy. EURATOM-CCFE Association. Abingdon 0X14 3DB, UK;

    IEK-4 (Plasma Physics), Forschungszentrum Juelich, Assoc. EURATOM-FZJ, D-52425Juelich. Germany;

    JET-EFDA. Culham Science Centre, Abingdon OX14 3DB, UK,EFDA-JETCIose Support Unit, Operation and Enhancements Dpt., Abingdon OXU 3DB, UK;

    IEK-4 (Plasma Physics), Forschungszentrum Juelich, Assoc. EURATOM-FZJ, D-52425Juelich. Germany;

    JET-EFDA. Culham Science Centre, Abingdon OX14 3DB, UK,Culham Centre for Fusion Energy. EURATOM-CCFE Association. Abingdon 0X14 3DB, UK;

    IEK-4 (Plasma Physics), Forschungszentrum Juelich, Assoc. EURATOM-FZJ, D-52425Juelich. Germany;

    IEK-4 (Plasma Physics), Forschungszentrum Juelich, Assoc. EURATOM-FZJ, D-52425Juelich. Germany;

    JET-EFDA. Culham Science Centre, Abingdon OX14 3DB, UK,Culham Centre for Fusion Energy. EURATOM-CCFE Association. Abingdon 0X14 3DB, UK;

    SINTEZScientific Technical Centre, D.V. Efremov SRIEA RUS-196641, St Petersburg, Russia;

    JET-EFDA. Culham Science Centre, Abingdon OX14 3DB, UK,Culham Centre for Fusion Energy. EURATOM-CCFE Association. Abingdon 0X14 3DB, UK;

    IEK-4 (Plasma Physics), Forschungszentrum Juelich, Assoc. EURATOM-FZJ, D-52425Juelich. Germany;

    JET-EFDA. Culham Science Centre, Abingdon OX14 3DB, UK,IEK-4 (Plasma Physics), Forschungszentrum Juelich, Assoc. EURATOM-FZJ, D-52425Juelich. Germany;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    divertor; tungsten; JET; plasma-facing components; power handling;

    机译:偏滤器钨喷射;等离子组件;功率处理;

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