| 基于MATLAB的AP1000核电机组反应堆DNBR特性研究 |
| |
| 引用本文： | 刘建全,石竟达,张柳柳,邱峰,贾浩,徐婷婷. 基于MATLAB的AP1000核电机组反应堆DNBR特性研究[J]. 上海电力学院学报, 2015, 31(6): 505-510 |
| |
| 作者姓名： | 刘建全 石竟达 张柳柳 邱峰 贾浩 徐婷婷 |
| |
| 作者单位： | 上海电力学院能源与机械工程学院,上海电力学院能源与机械工程学院,上海电力学院能源与机械工程学院,上海电力学院能源与机械工程学院,上海电力学院能源与机械工程学院,上海电力学院能源与机械工程学院 |
| |
| 摘 要： | 以AP1000核电机组反应堆偏离泡核沸腾比(DNBR)特性为研究对象.针对该反应堆堆芯功率与原型反应堆相比增加较为明显的状况,利用Matlab软件进行了DNBR的计算,并与原型反应堆进行了对比分析.计算结果表明:DNBR与临界热流密度(CHF)不是单纯的线性关系,而是随着轴向距离的增大,先减小后增大;各工况负荷情况的DNBR值均大于原型反应堆的对应值,AP1000反应堆运行安全特性明显高于常规核电机组反应堆;反应堆运行在高功率下的DNBR值明显大于运行在低功率下的DNBR值,反应性引入事故下,堆芯核功率的突然增加容易造成偏离泡核沸腾(DNB);质量流密度、含汽率、压力及进口欠热度等因素均对CHF产生影响,进而影响到DNBR值.
|
| 关 键 词： | 反应堆 临界热流密度 偏离泡核沸腾比 安全特性 |
| 收稿时间： | 2015-03-23 |
DNBR Characteristics Research Based on the MATLAB on AP1000 Nuclear Power Unit Reactor |
| |
| LIU Jianquan,SHI Jingd,ZHANG Liuliu,QIU Feng,QIU Rong and XU Tingting. DNBR Characteristics Research Based on the MATLAB on AP1000 Nuclear Power Unit Reactor[J]. Journal of Shanghai University of Electric Power, 2015, 31(6): 505-510 |
| |
| Authors: | LIU Jianquan SHI Jingd ZHANG Liuliu QIU Feng QIU Rong XU Tingting |
| |
| Affiliation: | School of Energy and Mechanical Engineering, Shanghai University of Electric Power, Shanghai 200090, China,School of Energy and Mechanical Engineering, Shanghai University of Electric Power, Shanghai 200090, China,School of Energy and Mechanical Engineering, Shanghai University of Electric Power, Shanghai 200090, China,School of Energy and Mechanical Engineering, Shanghai University of Electric Power, Shanghai 200090, China,School of Energy and Mechanical Engineering, Shanghai University of Electric Power, Shanghai 200090, China and School of Energy and Mechanical Engineering, Shanghai University of Electric Power, Shanghai 200090, China |
| |
| Abstract: | The characteristics of AP1000 nuclear power reactor departure from nucleate boiling ratio(DNBR) are studied. The reactor core nuclear power increases obviously compared with the prototype reactor, the DNBR is calculated using MATLAB software, and the result is compared with the prototype reactor. The calculation results show that the DNBR and critical heat flux(CHF) density is not of a simple linear relationship, with the increase of the axial distance decreasing first and then increasing. AP1000 DNBR is greater than the prototype reactor under every load conditions, and the security characteristics of AP1000 reactor is significantly higher. The high power DNBR is significantly higher than that of low power. Under the reactor insertion accidents, nuclear power sudden increase is likely to cause departure from nucleate boiling(DNB). The mass flow density, void fraction, pressure and inlet subcooling can affect the CHF which affects the value of DNBR. |
| |
| Keywords: | reactor critical heat flux departure from nuclear boiling ratio safety features |
| 本文献已被 CNKI 等数据库收录！ |
| 点击此处可从《上海电力学院学报》浏览原始摘要信息 |
|
点击此处可从《上海电力学院学报》下载全文 |
|
