检索规则说明:AND代表“并且”;OR代表“或者”;NOT代表“不包含”;(注意必须大写,运算符两边需空一格)
检 索 范 例 :范例一: (K=图书馆学 OR K=情报学) AND A=范并思 范例二:J=计算机应用与软件 AND (U=C++ OR U=Basic) NOT M=Visual
作 者:谢峰[1] 郗昭[1] 杨祖毛[1] Xie Feng;Xi Zhao;Yang Zumao(CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, China)
机构地区:[1]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,成都610213
出 处:《核动力工程》2018年第2期5-9,共5页Nuclear Power Engineering
基 金:国家自然科学基金青年基金资助(51506014)
摘 要:在核反应堆堆芯中由于存在固有反应性反馈效应,会发生耦合反应性反馈流动不稳定性,对反应堆运行造成不利影响。本文采用实验与理论相结合的方法,研究了反应性反馈(包括空泡反馈、温度反馈)对流动不稳定性的影响。采用计算机仿真模拟反应性反馈,分别在没有核反馈和有核反馈的情况下进行实验,研究了空泡反应性反馈系数(C_α)、慢化剂温度反应性反馈系数(C_t)对流动不稳定性的影响。通过实验研究,获得了反应性反馈对流动不稳定过程的影响规律。研究表明,C_α、C_t和元件时间常数(f_t)对流动不稳定过程及流动不稳定边界都有较大影响。As the existence of nuclear feedback in nuclear reactors,coupled nuclear-thermo-hydraulic instability will occur in the reactor. Coupled-nuclear-thermal-hydraulic instabilities were investigated employing experimental and theoretical methods in this paper. The experimental research on coupled nuclear-thermo-hydraulic instability in parallel channels was performed and the effect of the nuclear feedback on flow instability has been studied. The experiment is carried out with and without nuclear coupled respectively, and the effect of void reactivity coefficient and temperature reactivity coefficient on characteristic and boundaries of flow instability has been studied. Based on the experimental data, the tendency of the characteristics of effect is analyzed, and the stability boundaries is obtained. The results from the research in this paper show that: void reactivity coefficient, temperature reactivity coefficient and fuel time constant have a significant effect on characteristics and boundaries of flow instability.
分 类 号:TL33[核科学技术—核技术及应用]
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在链接到云南高校图书馆文献保障联盟下载...
云南高校图书馆联盟文献共享服务平台 版权所有©
您的IP:216.73.216.28