AP1000核电厂首循环CIPS风险评价  被引量:12

CIPS Risk Analysis for AP1000 PWR First Cycle

在线阅读下载全文

作  者:杨萍[1] 汤春桃[1] 

机构地区:[1]上海核工程研究设计院,上海200233

出  处:《核科学与工程》2012年第3期284-288,共5页Nuclear Science and Engineering

摘  要:CIPS(Crud Induced Power Shift),是指反应堆冷却剂系统内腐蚀积垢物在燃料棒表面沉积而导致轴向功率峰值向堆芯入口处偏移的现象。这一现象会影响核电厂运行的安全性,如:使降功率时轴向功率分布控制困难、停堆裕量减少、反应堆启堆时的临界工况评价出现偏差等,进而影响经济性。本文阐述了CIPS现象的成因、危害、风险降低途径,并使用3D核设计程序、热工-水力子通道程序和CIPS评价专用程序对AP1000核电厂首循环的CIPS风险进行了分析并给出了降低风险的建议。CIPS (Crud Induced Power Shift) is a shift in axial power towards the core inlet which results from the build up of crud on the fuel rods during operation. The impact of CIPS is that axial power distribution control is more difficult. The shutdown margin is also reduced after a trip. The increased reactivity difference between the HFP and HZP can also cause a misprediction of Estimated Critical Condition on the restart after trip or shutdown. In the report, the cause and impacts of CIPS and the ways to reduce the CIPS risk have been described. Additionally,3D nuclear design code,thermalhydraulic subchannel code and special CIPS analysis code have been combined together to analysis CIPS risk for AP1000 first cycle. At last,some advices on reducing CIPS risk have been presented.

关 键 词:CIPS 过冷泡核沸腾 硼酸沉积 注锌 

分 类 号:TL33[核科学技术—核技术及应用]

 

参考文献:

正在载入数据...

 

二级参考文献:

正在载入数据...

 

耦合文献:

正在载入数据...

 

引证文献:

正在载入数据...

 

二级引证文献:

正在载入数据...

 

同被引文献:

正在载入数据...

 

相关期刊文献:

正在载入数据...

相关的主题
相关的作者对象
相关的机构对象