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Morphological and structural effects on tungsten targets produced by fusion plasma pulses from a table top plasma focus

机译:台式等离子体聚焦聚变等离子体脉冲对钨靶的形态和结构影响

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摘要

A table top plasma focus device operating at hundreds of joules was used to simulate an equivalent damage factor than the obtained on the divertor in tokamak experiments. Using the ejected plasma produced after the pinch disruptions, the effects on tungsten targets from 50 cumulative plasma shocks with power fluxes per shot between 2.6 and 9200 kW cm~(-2) and with a duration time in the order of tens of nanoseconds (damage factor in the order of 10~0-10~3(W cm~(-2))s~(1/2)) were studied. Morphological analysis shows an increasing appearance of cracked surfaces with holes, fissures and defects, suggesting a potential progression of stress effects and a fast heat load that melts the surface, ending in thermal contractions that recrystallize the surface of the target. A structural analysis demonstrates a compressive stress development and suggests that part of the energy is released in the melting of the surface in case of a plasma shock with a power flux of 9.2MW cm~(-2), 75 ns duration pulse, 2.5 × 10~3(W cm~(-2))s~(1/2) damage factor. How to increase the damage factor by one order of magnitude up to the expected value from type I ELMs on the ITER divertor, i.e. 10~4(W cm~(-2)) s~(1/2) is discussed.
机译:使用在数百焦耳下工作的台式等离子体聚焦装置来模拟与托卡马克实验中在偏滤器上获得的等效损伤因子。使用收缩破坏后产生的喷射等离子体,每次发射的功率通量在2.6至9200 kW cm〜(-2)之间,持续时间约为数十纳秒(损坏),由50次累积等离子体冲击对钨靶产生的影响研究了约10〜0-10〜3(W cm〜(-2))s〜(1/2))因子。形态分析表明,带有孔,裂缝和缺陷的破裂表面的出现越来越多,这表明应力作用的潜在发展以及使表面熔化的快速热负荷,最终导致热收缩,使目标表面重结晶。结构分析表明出现了压应力,并表明在等离子冲击的情况下,以9.2MW cm〜(-2)的功率通量,75 ns的持续时间脉冲,2.5× 10〜3(W cm〜(-2))s〜(1/2)伤害系数讨论了如何将损伤因子增加一个数量级,直至达到ITER分流器上I型ELM的期望值,即10〜4(W cm〜(-2))s〜(1/2)。

著录项

  • 来源
    《Nuclear fusion》 |2015年第9期|093011.1-093011.8|共8页
  • 作者单位

    Comision Chilena de Energia Nuclear, Casilla 188-D, Santiago, Chile,Center for Research and Applications in Plasma Physics and Pulsed Power, P~4, Santiago-Curico Chile;

    Instituto de Fisica, Pontificia Universidad Cato1ica de Chile, Santiago 7820436, Chile;

    Comision Chilena de Energia Nuclear, Casilla 188-D, Santiago, Chile,Center for Research and Applications in Plasma Physics and Pulsed Power, P~4, Santiago-Curico Chile;

  • 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

    materials; nuclear fusion; plasma focus; damage factor;

    机译:材料;核聚变等离子聚焦破坏因素;
  • 入库时间 2022-08-18 00:42:33

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