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压水堆核电站蒸汽发生器传热管破裂监测方法评估

Evaluation of the SGTR Monitoring Method on PWR Nuclear Power Plants
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摘要 本文对蒸汽发生器传热管破裂事故(SGTR)进行了分类描述,分析了有、无操纵员干预的事故瞬态及后果差异。在此基础上,通过比较三种蒸汽发生器热管破裂监测方法的优缺点得到以下结论:主蒸汽管道辐射监测法响应速度快,可监测泄漏量大于化容系统补给能力的SGTR事故;蒸汽发生器排污辐射监测法、凝汽器与除氧器排出流取样监测法灵敏度较高,监测泄漏量小于化容系统补给能力的SGTR及事故后的分析更可靠。 For the steam generator tube rupture (SGTR) accident , this paper presents the different consequences with or without the operator intervention, compares the advantages and disadvantages of three kinds of radiation monitoring methods .The conclusion is that: the main steam pipe radiation monitoring method can quickly monitor SGTR accident when the leakage is greater than the makeup capacity of the chemical and volume control system (CVS) due to its less monitoring time,however the steam generator blowdown radiation monitoring method and the condenser and deaerator radiation monitoring method are more sensitive and more reliable, which can analyze the leakage less than the makeup capacity of CVS.
作者 闫超
出处 《核电工程与技术》 2013年第3期42-45,共4页 Nuclear Power Engineering and Technology
关键词 蒸汽发生器传热管破裂 辐射监测 泄漏率 SGTR. radiation monitorinm leakage rate
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