The invention provides a method and a device for determining reactor core parameters of a nuclear thermal propulsion reactor, and relates to the technical field of nuclear thermal propulsion, whereinthe method comprises the steps: acquiring a fluid-solid coupling heat transfer model of the nuclear thermal propulsion reactor; acquiring a target power parameter meeting aircraft performance constraints, and performing heat transfer calculation on the fluid-solid coupling heat transfer model based on the target power parameter to obtain multiple groups of design parameters meeting thermal constraints, wherein each group of design parameters comprises geometric parameters and thermal parameters; performing neutronics modeling and physical analysis based on the multiple groups of design parameters to obtain target geometric parameters and target thermal parameters meeting neutron physical constraints; and taking the target power parameters, the target thermal parameters and the target geometric parameters as reactor core design parameters of the nuclear thermal reactor. According to the method, the reliability of reactor core parameter design in the low-enrichment-degree concentrated uranium nuclear thermal propulsion reactor can be improved.
本发明提供了一种核热推进反应堆的堆芯参数确定方法及装置,涉及核热推进技术领域,该方法包括:获取核热推进反应堆的流固耦合传热模型;获取满足飞行器性能约束的目标动力参数,并基于目标动力参数对流固耦合传热模型进行传热计算,得到满足热工约束的多组设计参数;其中,每组设计参数中包括几何参数及热工参数;基于多组设计参数进行中子学建模及物理分析,得到满足中子物理约束的目标几何参数及目标热工参数;将目标动力参数、目标热工参数及目标几何参数作为核热反应堆的堆芯设计参数。本发明能够提升对低富集度浓缩铀核热推进反应堆中堆芯参数设计的可靠性。
Method and device for determining reactor core parameters of nuclear thermal propulsion reactor
核热推进反应堆的堆芯参数确定方法及装置
2021-01-08
Patent
Elektronische Ressource
Chinesisch
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