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

机译:低浓缩铀核热推进原型管的研制

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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:正在考虑将核热推进(NTP)用于未来人类执行的向火星等深空目的地的任务。 NTP将能够提供比最高性能的化学发动机几乎高一倍的比冲(I_(sp)),这将大大减少完成任务所需的推进剂数量,并缩短运输时间。美国宇航局正在与外部合作伙伴合作,研究开发可满足未来任务需求的低浓铀(LEU)发动机概念。当前的点设计需要一个堆芯内束管,这些束管的功能部分是预热氢推进剂,该推进剂将驱动涡轮泵并容纳氢化锆(ZrH_(1.8))减速剂以使中子热化。光谱。一个小的开发团队的任务是通过考虑详细的机械设计和基于特定设计约束的材料选择来使拉杆管概念成熟。该系统的材料和热机械响应是通过构建小规模拉杆试验台进行评估的。为了确定横拉管上的温度梯度,入口和出口压力的变化以及潜在的材料降解,开发了一种实验测试设备。在一定的质量流量和炉温(-200-500°C)范围内使用了氮气,氩气和氢气。该项目除了创建和量化ZrH样品外,还最终完成了测试台的建设和初步测试。未来的工作旨在扩大测试平台的规模,以有效地测试全长的拉管组件。

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