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核反馈对堆芯并联通道流动不稳定性的影响研究

发表时间:2013-10-31  浏览量:1533  下载量:587
全部作者: 鲁晓东,巫英伟,秋穗正,苏光辉,田文喜
作者单位: 西安交通大学能源与动力工程学院,动力工程多相流国家重点实验室
摘 要: 基于并联多通道模型开发了堆芯并联通道流动不稳定性热工程序,耦合三维物理程序DONJON开发了耦合堆芯并联通道流动不稳定性分析程序。运用该耦合程序对6×6堆芯的流动不稳定性进行分析。结果表明:有核反馈时,受扰动通道和不受扰动通道的振荡幅值相等,通道的进口流量脉动和功率脉动存在相位差;核反馈能增强堆芯并联通道系统的流动稳定性。
关 键 词: 核动力工程技术;核反馈;并联通道;核热耦合;流动不稳定
Title: Effect of neutronic feedback on flow instability in parallel channels of the reactor core
Author: LU Xiaodong, WU Yingwei, QIU Suizheng, SU Guanghui, TIAN Wenxi
Organization: State Key Laboratory on Power Engineering and Multi-Phase Flow, School of Energy and Power Engineering, Xi�an Jiaotong University
Abstract: Based on parallel multi-channels model, a thermal-hydraulic code for flow instability in parallel channels of the reactor core has been developed. A coupling code has been developed by coupling the thermal-hydraulic code with the DONJON 3D neutron kinetic code. The flow instability for the reactor core is performed using the coupling code. The results show that the disturbed channel and undisturbed channel have the same oscillation amplitude of inlet flow rate with neutronic feedback, a phase difference exists between the inlet flow rate oscillation and the power oscillation in one channel. The flow stability of parallel channels of the reactor core can be stablized by neutronic feedback.
Key words: nuclear power engineering and technology; neutronic feedback; parallel channel; neutronic-thermohydraulic coupling; flow instability
发表期数: 2013年10月第20期
引用格式: 鲁晓东,巫英伟,秋穗正,等. 核反馈对堆芯并联通道流动不稳定性的影响研究[J]. 中国科技论文在线精品论文,2013,6(20):1979-1985.
 
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