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Space Nuclear Power and Power Propulsion Systems Basedon the Reactor with External Solid Core Heat Conversion

机译:基于具有外部固体堆芯热转化的反应堆的空间核动力与动力推进系统

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摘要

Nuclear fission reactors with an external conversion of the solid phase core heat arernconsidered both in Russia and abroad as a compact power source of a long-term use which isrnindependent of a space vehicle position.rnFor the last years Russia has accumulated an experience in development of both the power and thernpower- propulsion systems including the systems based on the use of the reactors designed on thernNuclear Thermal Propulsion (NTP) technology. The results of experimental development of thernmain structural elements of the reactors with solid phase cores of different power andrnconfigurations are available. At the same time, the systems are under consideration in which a fastrnneutron reactor and turbogenerator system working by the Brayton thermodynamic cycle are thernbasic components.rnOne of the two variants to organize heat removal is contemplated in the reactor structure:rn-by a heterogeneous core with the rod fuel elements cooled by a longitudinally enteringrncoolant;rn-by a core of a particle bed type with fuel spheres and longitudinal-lateral distribution of therncoolant by a scheme from periphery to center.rnCarbonitride fuel with highly enriched uranium is supposed to be used in both configurations.rnEquipping the space vehicles with such reactors is carried out by two types of the systems, namely:rnby Bimodal Nuclear Thermal Propulsion (BNTP) and Nuclear Power Plant (NPP). For allrnvariants of using BNTP and NPP a preliminary development of their structure has been conductedrnand thermohydraulic, neutronic and dynamic calculations have been performed. The mainrnstructural and technological parameters of each system under consideration have beenrndetermined. The measures to ensure their nuclear and radiation safety, and the measures tornachieve high reliability in all modes of their operation have been substantiated. Both heat pipe andrndroplet variants of a radiator are considered as the NPP's radiators in the systems to utilize anrnunused heat.
机译:在俄罗斯和国外,具有固相核心热量的外部转换的核裂变反应堆被认为是一种长期使用的紧凑型动力源,与空间飞行器的位置无关。在过去的几年中,俄罗斯积累了发展核动力堆的经验。电力和电力推进系统,包括基于使用核热推进(NTP)技术设计的反应堆的系统。具有不同功率和构型的固相核反应堆的主要结构元件的实验开发结果是可用的。同时,正在考虑以布雷顿热力学循环为基础的快中子反应堆和涡轮发电机系统是基本组成部分的系统。在反应堆结构中,考虑了组织排热的两种变体之一:棒状燃料元件由纵向进入的冷却剂冷却;由颗粒床类型的芯,具有燃料球,冷却剂的纵向-横向分布是从外围到中心的方案。应该使用高浓缩铀的碳氮化物燃料在两种配置中,装有这种反应堆的航天器都是通过两种类型的系统进行的,即:双峰核热推进(BNTP)和核电站(NPP)。对于使用BNTP和NPP的所有变体,已经对其结构进行了初步开发,并进行了热工液压,中子和动态计算。确定了所考虑的每个系统的主要结构和技术参数。确保其核和辐射安全的措施以及在其所有运行方式中实现高可靠性的措施均得到证实。散热器的热管和液滴的两种变体都被视为系统中NPP的散热器,以利用废热。

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  • 来源
  • 会议地点 San Diego CA(US);San Diego CA(US)
  • 作者单位

    Russian Research Center “Kurchatov Institute”, Russia;

    Joint Stock Company “Chemical Automatics Design Bureau”, Russia;

    Federal State Unitary Enterprise “Research and Development Institute of Power Engineering”, RussiarnP.O.B. 788, Moscow, 101000 Russia, Tel: 7(095)263-74-35, Fax: 7(095) 264-75-32, Email: abalina@nikiet.ru;

    Federal State Unitary Enterprise, Research and Development Institute, Scientific-Production Association “Luch”;

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