毛晨瑞, 吉宇, 孙俊, 郎明刚, 石磊. 核热推进系统分析程序模型与计算方法初步研究[J]. 原子能科学技术, 2024, 58(3): 680-688. DOI: 10.7538/yzk.2023.youxian.0506
引用本文: 毛晨瑞, 吉宇, 孙俊, 郎明刚, 石磊. 核热推进系统分析程序模型与计算方法初步研究[J]. 原子能科学技术, 2024, 58(3): 680-688. DOI: 10.7538/yzk.2023.youxian.0506
MAO Chenrui, JI Yu, SUN Jun, LANG Minggang, SHI Lei. Preliminary Research on Model and Computational Method of System Analysis Program in Nuclear Thermal Propulsion[J]. Atomic Energy Science and Technology, 2024, 58(3): 680-688. DOI: 10.7538/yzk.2023.youxian.0506
Citation: MAO Chenrui, JI Yu, SUN Jun, LANG Minggang, SHI Lei. Preliminary Research on Model and Computational Method of System Analysis Program in Nuclear Thermal Propulsion[J]. Atomic Energy Science and Technology, 2024, 58(3): 680-688. DOI: 10.7538/yzk.2023.youxian.0506

核热推进系统分析程序模型与计算方法初步研究

Preliminary Research on Model and Computational Method of System Analysis Program in Nuclear Thermal Propulsion

  • 摘要: 核热推进(NTP)系统具有高比冲、大推力和工作时间长等特点,在深空探测和轨道机动等方面具有明显的优势。系统性能分析是NTP系统研发与设计的重要内容。结合对国际历史上已开发程序的分析以及现阶段的研发需求,将系统性能分析划分为稳态设计点性能分析与优化、稳态非设计点性能分析以及瞬态性能分析3个主要环节。在清华大学核能与新能源技术研究院自主开发的核动力发动机系统分析程序PANES基础上,提出了基于"流网-热网"的系统分析程序框架,并建立了反应堆中子动力学与涡轮泵动态特性等数学模型,提出了对应的计算分析方法,拓展了原程序的功能。该工作为NTP系统设计方法的进一步研究和应用提供了重要基础。

     

    Abstract: The nuclear thermal propulsion (NTP) boasts advantages such as high specific impulse, substantial thrust, and extended operating time, giving it a clear edge in deep space exploration and orbital maneuvers. To fully harness the potential of NTP, a comprehensive system performance analysis is crucial to ensure reliability and efficiency under various operational conditions. This study provided an overview of the historical development and current status of nuclear thermal propulsion system analysis programs, both nationally and internationally. It also conducted an in-depth analysis of programs utilized in projects such as NERVA and SNTP. Building on an examination of historical international program advancements and current research requirements, system performance analysis is categorized into three primary components:steady-state performance design and optimization, steady-state off-design performance analysis, and transient performance analysis. Based on the independently developed program for analyzing nuclear engine systems (PANES) at Institute of Nuclear and New Energy Technology, Tsinghua University, an integrated NTP system analysis program framework based on "flow network-heat network" was proposed. The one-dimensional flow network model employed a concept similar to the staggered grid commonly used in computational fluid dynamics (CFD). It separately handled the momentum conservation equation in the resistance/inertia segment and the continuity and energy conservation equations in the capacitance segment. The thermal network model was solved based on the solid energy equation considering heat capacity. Coupled calculations of the thermal network and flow network were achieved by considering heat exchange in the capacitance segment of the flow network. Specifically, a point reactor model based on backward Euler (BE) or Crank-Nicolson (CN) time discretization formats was established to facilitate the calculation of power produce processes. To enhance the understanding and optimization of turbine performance, a turbine model was developed, employing iterative methods to determine mass flow based on turbine inlet parameters, pressure ratios, and characteristic curves. Additionally, to accurately simulate centrifugal pump behavior, a centrifugal pump model based on Suter curves was implemented. The integration of these models provides a comprehensive approach for considering and effectively designing and optimizing the performance of turbine and pump components within the NTP system. This work lays a crucial foundation for further research and application of NTP system design methods, paving the way for future advancements in space exploration and offering exciting prospects for upcoming space missions.

     

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