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Helium-cooled divertor module for fusion devices

机译:用于融合器件的氦气冷却偏移器模块

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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.
机译:TPX,NET和ITER等先进的融合机必须设计为处理大约5到15 MW / m $ + 2 $ /在分解区域的热量通量。目前的概念设计使用水冷。然而,在这些机器中,泄漏将具有非常严重的后果。如果泵送功率可以限于合理的值,则用氦气如氦气的气体冷却是非常有吸引力的替代方案。比较了通过氦气冷却分流器的不同概念。发现通过在4MPa(580psia)的压力下使用氦气去除显着的稳态热通量(10至20 mW / m $ + 2 $)是可行的,并且泵送电量小于0.5%通过使用优化的设计拆除了POWER。从泵送功率考虑,各种概念排名按以下顺序:胶印翅片(最佳),翅片,喷射,3-D粗糙度,2-D粗糙度,平滑管(最差)。基于该研究的模块已经设计和制造,用于稳定状态操作,以10 MW / m $ + 2 $ /,并在桑迪亚国家实验室的高热助熔机构测试。本文还介绍了氦气冷却浸渍器的一些初步研究。

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