Coupled multi-physics analysis of low-enriched uranium nuclear thermal propulsion reactors

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Li Wei , Liu Xiaojing , Chai Xiang , Liu Zijing , Zhao Pengcheng
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Abstract

The growing demand for high-performance propulsion systems in aerospace has highlighted that current multi-physics coupling technologies cannot accurately assess the performance and safety of low-enriched uranium nuclear thermal propulsion reactors (LEU-NTPRs) under extreme conditions. Accordingly, this study employs advanced multi-physics coupling methods to investigate the performance, safety, and thermoelastic behavior of LEU-NTPR assemblies and their core geometries under several extreme boundary conditions, providing a scientific basis for reactor design. By utilizing OpenFOAM, a multi-region neutron transport-conjugate heat transfer coupling solver is developed to perform pin-by-pin multi-physics coupling calculations for reactor assemblies and full-core geometries. Both the neutron transport and conjugate heat transfer equations are solved, and the resulting steady-state temperature distribution is used as the input for thermoelastic calculations. Thermoelastic analyses are conducted using the solid4Foam solver of OpenFOAM by assuming a small strain to evaluate the displacement and equivalent thermal stress distributions. The assembly coupled simulation shows a significantly improved prediction accuracy for fuel temperature compared to non-coupled methods. Core-coupled simulations confirm that the conceptual design adheres to physical and thermal engineering standards. A thermoelastic analysis reveals that the maximum thermal stress is ∼ 246 MPa, while the maximum fuel displacement reaches 7.1 mm. These findings suggest that thermal stress, particularly in regions with significant temperature gradients, can be a critical factor limiting core power output. By adjusting the core inlet flow rates, the maximum assembly temperature is controlled within safe limits while achieving uniform coolant outlet temperatures. The proposed multi-regional coupling approach enhances the prediction accuracy for the performance, safety, and thermoelastic characteristics of LEU-NTPRs under extreme conditions, while ensuring a high specific impulse in propulsion systems.
低浓缩铀核热推进反应堆的耦合多物理场分析
航空航天领域对高性能推进系统日益增长的需求突出表明,目前的多物理场耦合技术无法准确评估低浓缩铀核热推进反应堆(leu - ntpr)在极端条件下的性能和安全性。因此,本研究采用先进的多物理场耦合方法,研究了几种极端边界条件下LEU-NTPR组件及其堆芯几何形状的性能、安全性和热弹性行为,为反应堆设计提供科学依据。利用OpenFOAM,开发了一个多区域中子输运共轭传热耦合求解器,用于对反应堆组件和全堆芯几何形状进行逐针多物理场耦合计算。求解了中子输运方程和共轭传热方程,并将得到的稳态温度分布作为热弹性计算的输入。利用OpenFOAM的solid4Foam求解器进行热弹性分析,假设小应变,计算位移和等效热应力分布。装配耦合仿真结果表明,与非耦合方法相比,装配耦合方法对燃料温度的预测精度有显著提高。核心耦合模拟证实了概念设计符合物理和热工标准。热弹性分析表明,最大热应力为~ 246 MPa,最大燃油排量为7.1 mm。这些发现表明,热应力,特别是在具有显著温度梯度的地区,可能是限制核心功率输出的关键因素。通过调整堆芯进口流量,最大装配温度被控制在安全范围内,同时实现均匀的冷却剂出口温度。提出的多区域耦合方法提高了极端条件下低浓缩铀- ntpr性能、安全性和热弹性特性的预测精度,同时确保了推进系统的高比冲。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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