首页> 外文会议>Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety Oct 15-18, 2000 Denki Bldg., Chuo-ku, Fukuoka, Japan >A LINEAR MODEL TO STUDY THE OUT-OF-PHASE INSTABILITY IN THE BOILING CHANNELS OF THE ADVANCED HEAVY WATER REACTOR
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A LINEAR MODEL TO STUDY THE OUT-OF-PHASE INSTABILITY IN THE BOILING CHANNELS OF THE ADVANCED HEAVY WATER REACTOR

机译:研究高级重水器沸腾通道内相外不稳定性的线性模型

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In order to investigate the out-of-phase instability in the boiling channels of the AHWR, a linear analytical model has been developed. The model considers homogeneous two-phase flow for the coolant, a coupled multipoint kinetics model for the neutron field dynamics and a lumped fuel heat transfer model. The characteristic equation has been derived considering the interactions of multiple parallel channels of the reactor with the inlet and outlet feeders and the external loop while operating under natural circulation condition. The thermal hydraulic and coupled neutronic-thermohydraulic out-of-phase stability behaviour of the reactor has been studied. The effect of coupling coefficient which determines the reactivity contributed by the interaction between subcores during an out-of-phase instability has been predicted. The results of the present model has been compared with that of a modal point kinetics model. The effect of radial power distribution and channel inlet orificing on the stability of the reactor has also been investigated.
机译:为了研究AHWR沸腾通道中的异相不稳定性,开发了线性分析模型。该模型考虑了冷却剂的均相两相流,中子场动力学的耦合多点动力学模型以及集总燃料传热模型。在自然循环条件下运行时,考虑到反应器的多个平行通道与入口和出口进料器以及外部回路的相互作用,得出了特征方程。研究了反应堆的热工水力耦合和中子热工耦合的异相稳定性行为。已经预测了耦合系数的影响,该系数决定了在异相不稳定性期间子核心之间的相互作用所贡献的反应性。本模型的结果已与模态点动力学模型的结果进行了比较。还研究了径向功率分布和通道入口孔口对反应堆稳定性的影响。

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