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Helium-cooled divertor module for fusion devices

机译:用于聚变设备的氦冷分流器模块

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Abstract: The advanced fusion machines such as TPX, NET, and ITER have to be designed to handle a heat flux of about 5 to 15 MW/m$+2$/ in the diverter region. The present conceptual designs use water cooling. However water leaks will have very serious consequences in these machines. Cooling with a gas like helium is a very attractive alternative, if the pumping power can be limited to a reasonable value. Different concepts to cool diverter by helium gas were compared. It was found that it is feasible to remove significant steady state heat flux (10 to 20 MW/m$+2$/) by using helium at a pressure of 4 MPa (580 psia) and with pumping power less than 0.5% of the power removed, by using optimized designs. From pumping power consideration, various concepts rank in the following order: offset fins (best), fins, jets, 3-D roughness, 2-D roughness, smooth tubes (worst). A module based on this study has been designed and fabricated for a steady state operation at 10 MW/m$+2$/ and was tested at the High Heat Flux facility at Sandia National Laboratory. This paper also presents some preliminary studies of helium cooled ITER diverter. !9
机译:摘要:先进的聚变机,例如TPX,NET和ITER,必须设计为在分流区域处理大约5至15 MW / m $ + 2 $ /的热通量。本概念设计使用水冷。但是,漏水会对这些机器造成非常严重的后果。如果可以将抽气功率限制在一个合理的值,那么用氦气等气体进行冷却是非常有吸引力的选择。比较了用氦气冷却分流器的不同概念。发现在4 MPa(580 psia)的压力下使用氦气且泵送功率小于冷凝器的0.5%时,去除大量稳态热通量(10至20 MW / m $ + 2 $ /)是可行的。通过优化设计消除了电源。考虑到泵浦功率,各种概念按以下顺序排列:偏置鳍片(最佳),鳍片,射流,3-D粗糙度,2-D粗糙度,光滑管(最差)。已经设计和制造了基于这项研究的模块,以10 MW / m $ + 2 $ /的稳态运行,并在桑迪亚国家实验室的高通量设施中进行了测试。本文还介绍了氦冷却的ITER分流器的一些初步研究。 !9

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