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
机构地区:[1]中国原子能科学研究院
出 处:《核科学与工程》1996年第3期193-199,共7页Nuclear Science and Engineering
摘 要:用RELAPS/MOD2程序和MARCH3程序对秦山核电厂多种假想SGTR事故及其所致严重事故进行了计算,分析了主要事故序列的事故进程,估算了严重事故下的熔堆时序,探讨了一些有效的事故处置措施及其干预效果。SGTR accident is one of the most frequent major accidents, in which operators have to intervene immediately in order to prevent the broken SG from overfilling. If the broken SG overfill leads to the safety valve stuck open, severe accident may occur.RELAP5/MOD2 and MARCH3 codes are applied to process analysis of Qinshan Nuclear Power Plant SGTR accidents and severe accidents initiated by SGTR. Time sequences for core melting are estimated. Some accident managements and their effects are discussed. The analysis results by the codes show that the following accident sequences may lead to coremelt, such as SGTR with broken SG safety valve stuck open, SGTR with loss of AKW, more ruptured tubes SGTR with failure of safety injection system, and SGTR with failure of both SI and AFW.The experiences of accident managements show that the coremelt can be prevented by means of depressurizing RCS by feed - bleed of intact SG, by openning pressurizer PORVs manually, or by primary system bleed with secondary system feed. The probability for SGTR events leading to coremelt can be considerably reduced by the above managements.
关 键 词:秦山核电厂 蒸汽发生器传热管破裂事故 严重事故 序列分析 事故处置
分 类 号:TM623.4[电气工程—电力系统及自动化]
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:216.73.216.145