首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >RACLETTE - A MODEL FOR EVALUATING THE THERMAL RESPONSE OF PLASMA FACING COMPONENTS TO SLOW HIGH POWER PLASMA TRANSIENTS .2. ANALYSIS OF ITER PLASMA FACING COMPONENTS
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RACLETTE - A MODEL FOR EVALUATING THE THERMAL RESPONSE OF PLASMA FACING COMPONENTS TO SLOW HIGH POWER PLASMA TRANSIENTS .2. ANALYSIS OF ITER PLASMA FACING COMPONENTS

机译:RACLETTE-评价等离子面对组件对慢速高功率等离子瞬态热响应的模型2。等离子面对部件的分析

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The transient thermal model RACLETTE (acronym of Rate Analysis Code for plasma Energy Transfer Transient Evaluation) described in part T of this paper is applied here to analyse the heat transfer and erosion effects of various slow (100 ms-10 s) high power energy transients on the actively cooled plasma facing components (PFCs) of the International Thermonuclear Experimental Reactor (ITER). These have a strong bearing on the PFC design and need careful analysis. The relevant parameters affecting the heat transfer during the plasma excursions are established. The temperature variation with time and space is evaluated together with the extent of vaporisation and melting (the latter only for metals) fur the different candidate armour materials considered for the design (i.e., Be for the primary first wall, Be and CFCs for the limiter, Be, W, and CFCs for the divertor plates) and including for certain cases low-density vapour shielding effects. The critical heat flux, the change of the coolant parameters and the possible severe degradation of the coolant heat removal capability that could result under certain conditions during these transients, for example for the limiter, are also evaluated. Based on the results, the design implications on the heat removal performance and erosion damage of the various ITER PFCs are critically discussed and some recommendations are made for the selection of the most adequate protection materials and optimum armour thickness. [References: 21]
机译:本文T部分中描述的瞬态热模型RACLETTE(等离子体能量传递瞬态评估速率分析代码的缩写)在这里用于分析各种慢速(100 ms-10 s)高功率能量瞬变的热传递和腐蚀效应。在国际热核实验反应堆(ITER)的主动冷却的面向等离子体的组件(PFC)上使用。这些与PFC设计有很大关系,需要仔细分析。建立了影响等离子体偏移期间传热的相关参数。随时间和空间的温度变化以及汽化和熔化的程度(后者仅针对金属)连同设计中考虑使用的不同候选装甲材料(即,Be用于主要的第一壁,Be和CFC用于限制器)一起进行评估。 ,Be,W和分流板的CFC),并且在某些情况下还包括低密度蒸汽屏蔽作用。还评估了临界热通量,冷却剂参数的变化以及在这些瞬态过程中(例如限制器)在某些条件下可能导致的冷却剂散热能力的严重下降。根据结果​​,对各种ITER PFC的除热性能和腐蚀破坏的设计意义进行了严格讨论,并提出了一些建议,以选择最合适的防护材料和最佳装甲厚度。 [参考:21]

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