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Performance of tungsten based materials and components under ITER and DEMO relevant steady-state thermal loads

机译:钨基材料和组件在ITER和DEMO相关稳态热负荷下的性能

摘要

In nuclear fusion devices the surfaces directly facing the plasma are irradiated with high energy fluxes. The most intense loads are deposited on the divertor located at the bottom of the plasma chamber, which has to withstand continuous heat loads with a power density of several MW/m² as well as transient events. These are much shorter (in the millisecond and sub-millisecond regime) but deposit a higher power densities of a few GW/m². The search for materials that can survive to those severe loading conditions led to the choice of tungsten which possesses advantageous attributes such as a high melting point, high thermal conductivity, low thermal expansion and an acceptable activation rate. These properties made it an attractive and promising candidate as armor material for divertors of future fusion devices such as ITER and DEMO. For the DEMO divertor, conceptual studies on helium-cooled tungsten plasma-facing components were performed. The concept was realized and tested under DEMO specific cyclic thermal loads. The examination of the plasma-facing components by microstructural analyses before and after thermal loading enabled to determine the mechanisms for components failure. Among others, it clearly showed the impact of the tungsten grade and the thermal stress induced crack formation on the performance of the armor material and in general of the plasma-facing component under high heat loads. A tungsten qualification program was launched to study the behaviour of various tungsten grades, in particular the crack formation, under fusion relevant steady-state thermal loads. In total, seven commercially available materials from two industrial suppliers were investigated. As the material's thermal response is strongly related to its microstructure, this program comprised different material geometries and manufacturing technologies. It also included the utilization of an actively cooled specimen holder which has been designed to perform sophisticated material tests at different surface temperatures. The steady-state thermal loading with superimposed transient thermal loading was induced by high frequency scanning of the electron beam. The steady-state thermal loading was performed with different power densities, surface temperatures and cycle numbers. The cracking threshold was investigated in a temperature range of 1000 to 1900°C. Once cracks occurred, the surface temperature had no impact on the crack network of the loaded surface. The cracks grew in depth with increasing the cycle number. However, under all loading conditions, crack depths were still limited in a shallow region, namely below 100 µm. One disadvantage of tungsten is its high brittleness at room temperature which makes the manufacturing of tungsten parts challenging as it requires suitable machining techniques. The examination of the helium-cooled tungsten plasma-facing components revealed cracks in as-machined surfaces. For a better understanding of the performance of plasma-facing components it was necessary to estimate the impact of pre-cracked surfaces on the components' degradation under high heat fluxes. Therefore, in the frame of the tungsten qualification program, specimens with defect-free and pre-cracked surfaces were exposed to high heat fluxes. Surface processing by electric discharge machining (EDM) led to pre-cracked surfaces and defect-free surfaces were achieved by polishing. EDM-pre-cracking resulted in a high crack density consisting of inter- and intra-granular cracks, which did not change after thermal loading. Even more, the cracks did not grow with the cycle number in contrast to thermo-mechanical induced cracks on polished surfaces which occurred at lower crack density.
机译:在核聚变装置中,直接面对等离子体的表面被高能量通量照射。最强的负载沉积在位于等离子腔室底部的分流器上,该分流器必须承受连续的热负载,功率密度为数MW /m²,并具有瞬态事件。它们要短得多(在毫秒级和亚毫秒级),但是沉积的功率密度更高,只有几GW /m²。对可以在那些苛刻的负载条件下生存的材料的研究导致选择钨,钨具有诸如高熔点,高导热率,低热膨胀和可接受的活化速率的有利属性。这些特性使其成为未来的聚变设备(如ITER和DEMO)转向器的装甲材料,具有吸引力和前途。对于DEMO偏滤器,对氦冷却的钨等离子体等离子体组件进行了概念研究。这个概念是在DEMO特定的循环热负荷下实现和测试的。在热加载之前和之后,通过微结构分析对面向等离子体的部件进行检查,从而可以确定部件失效的机理。除其他外,它清楚地表明了钨等级和热应力引起的裂纹形成对装甲材料的性能以及在高热负荷下总体上面向等离子体的部件的性能的影响。发起了钨资格认证计划,以研究在熔化相关的稳态热负荷下各种钨等级的行为,特别是裂纹形成。总共调查了来自两个工业供应商的七种商用材料。由于材料的热响应与其微观结构密切相关,因此该程序包含了不同的材料几何形状和制造技术。它还包括采用主动冷却的样品架,该样品架设计用于在不同的表面温度下进行复杂的材料测试。通过对电子束进行高频扫描,可以得到稳态热负荷和瞬态热负荷的叠加。用不同的功率密度,表面温度和循环次数执行稳态热负载。在1000至1900°C的温度范围内研究了开裂阈值。一旦出现裂纹,表面温度对加载表面的裂纹网络没有影响。随着循环次数的增加,裂纹的深度增加。但是,在所有载荷条件下,裂纹深度仍局限于较浅的区域,即100 µm以下。钨的一个缺点是其在室温下的高脆性,这使得钨零件的制造具有挑战性,因为它需要合适的机加工技术。对氦冷却的钨等离子体等离子体部件的检查发现,加工后的表面存在裂纹。为了更好地了解面向等离子部件的性能,有必要估算预破裂表面在高热通量下对部件降解的影响。因此,在钨合金鉴定计划的框架内,具有无缺陷和预破裂表面的试样暴露于高热通量下。通过放电加工(EDM)进行的表面处理导致了预裂表面,并且通过抛光获得了无缺陷的表面。 EDM预开裂导致由晶间和晶内裂纹组成的高裂纹密度,在热负荷后,裂纹密度没有变化。甚至与以较低的裂纹密度发生的抛光表面上的热机械引起的裂纹相反,裂纹不随循环次数而增长。

著录项

  • 作者

    Ritz Guillaume Henri;

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  • 年度 2011
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  • 原文格式 PDF
  • 正文语种 eng
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