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Development of a Prototypic Tie-Tube for Low-Enriched Uranium Nuclear Thermal Propulsion

机译:用于低富富铀核热推进的原型系管的开发

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Nuclear thermal propulsion (NTP) is under consideration for future human missions to deep space destinations such as Mars. NTP will be capable of providing a specific impulse (I_(sp)) nearly double that of the highest performing chemical engines, which significantly reduces the amount of propellant required for to complete a mission and with reduced transit time. NASA in collaboration with external partners is investigating development a low-enriched uranium (LEU) engine concepts for future mission needs. The current point design calls for an array of in-core tie-tube, which function in part to pre-heat the hydrogen propellant that will drive the turbo-pump and house the zirconium hydride (ZrH_(1.8)) moderator to thermalize the neutron spectrum. A small development team was tasked to mature a tie tube concept by considering detailed mechanical design and materials selection based upon specific design constraints. The material and thermo-mechanical response of the system was evaluated through the construction of a sub-scale tie-tube test rig. An experimental test apparatus was developed in order to determine temperature gradients across the tie-tube, variations in inlet and outlet pressure, and potential material degradation. Nitrogen, argon, and hydrogen was used over a range of mass flow rates and furnace temperatures (-200 - 500°C). The project culminated in the construction and preliminary testing of the test rig in addition to the creation and quantification of ZrH samples. Future work aims to scale the test rig to effectively test full-length tie-tube elements.
机译:核热推进(NTP)正在考虑为未来的人类任务深空目的地,如火星。 NTP将能够提供比冲(I_(SP))的近两倍的性能最高的化学引擎,显著减少了完成任务所需的推进剂的量和减少运输时间的那个。 NASA与外部伙伴的合作正在研究开发用于未来的任务需求的低浓缩铀(LEU)发动机概念。当前点设计要求在核提携管的阵列,其功能部分地预加热氢推进剂将驱动涡轮泵和容纳锆氢化物(ZrH_(1.8))调节剂到热化中子光谱。一个小的开发团队的任务是通过考虑基于特定的设计约束详细的机械设计和材料的选择成熟领带管概念。该系统的材料和热机械响应通过一个分刻度领带管试验台的结构进行评价。实验试验装置,以便确定在入口和出口压力横跨提携管的温度梯度,变化的发展,和潜在的材料降解。氮气,氩气和氢气被用于在一定范围的质量流量和炉的温度(-200 - 500°C)的。该项目的建设和除ZRH样品的创建和定量试验台的初步测试达到了高潮。今后的工作目的是按比例的试验装置有效地测试全长领带管元件。

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