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A computational model for an open-cycle gas core nuclear rocket.

机译:一种开环气核核火箭的计算模型。

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A computational model of an open-cycle Gas Core Nuclear Rocket (GCR) is developed. The model evaluates the rocket performance of an open-cycle GCR as a function of design and operational parameters. The primary output of the model is the specific impulse and thrust of the rocket.; The solution is divided into two distinct areas--thermal-hydraulics and neutronics. To obtain the thermal-hydraulic solution, a computer code is written which solves the Navier-Stokes, energy, and species diffusion equations. A spatially implicit solution is obtained by a direct solver that is developed specifically for the code. The two-dimensional transport code TWODANT is used to obtain the neutronics solution. The important requirements of the neutronics model are the ability to handle neutron upscattering and a highly inhomogeneous mesh. The thermal-hydraulic and neutronic models are coupled, and the solution proceeds in an iterative manner until a consistent power density profile is obtained.; Various open-cycle gas core nuclear rocket designs are evaluated. First, it is assumed that the fuel and propellant do not mix. In this ideal case, it is found that the limiting factor in determining thrust and specific impulse is the maximum allowable wall heat flux. Next, a neutronic study is performed on a simplified homogeneous open-cycle GCR design. The effect of changing the fuel/propellant densities and temperatures on the multiplication factor k-eff is studied, as is the use of alternate fuels and propellants. Following this simplified neutronic study, the results from a complete thermal-hydraulic/neutronic solution are presented. The thermodynamic and nuclear properties of the reactor are studied in detail, particularly density and neutron flux. These results provide insight into the underlying physics of an open-cycle GCR, as well demonstrate the capabilities of the model. Next, a parametric design study is conducted which examines the rocket performance of the open-cycle GCR as a function of various design and operational parameters. It is found that fuel containment is very adversely effected by high reactor power or rocket acceleration. Finally, some innovative concepts are discussed that could help improve fuel containment.
机译:建立了开放循环气核核火箭(GCR)的计算模型。该模型根据设计和运行参数评估开放循环GCR的火箭性能。该模型的主要输出是火箭的比冲和推力。解决方案分为两个不同的领域-热工液压和中子学。为了获得热工液压解决方案,编写了一个计算机代码,用于求解Navier-Stokes,能量和物质扩散方程。空间隐式解决方案是由专门为代码开发的直接求解器获得的。二维运输代码TWODANT用于获得中子学解决方案。中子学模型的重要要求是能够处理中子向上散射和高度不均匀的网格。热工和中子模型被耦合,并且解决方案以迭代方式进行,直到获得一致的功率密度曲线为止。评估了各种开放循环气核核火箭设计。首先,假设燃料和推进剂没有混合。在这种理想情况下,发现确定推力和比冲的限制因素是最大允许壁热通量。接下来,对简化的均相开放循环GCR设计进行中子研究。研究了改变燃料/推进剂密度和温度对倍增系数k-eff的影响,以及替代燃料和推进剂的使用。通过简化的中子学研究,提出了完整的热工/中子解决方案的结果。详细研究了反应堆的热力学和核性质,特别是密度和中子通量。这些结果提供了对开放周期GCR的基础物理的洞察力,并演示了该模型的功能。接下来,进行了参数设计研究,研究了开放循环GCR的火箭性能与各种设计和运行参数的关系。已经发现,高反应堆功率或火箭加速对燃料的容纳有非常不利的影响。最后,讨论了一些创新的概念,这些概念可以帮助改善燃料围堵。

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