DVI管线破裂始发严重事故的IVR分析  

Analysis on IVR in Severe Accident Induced by DVI Line Break

作　　者：李京喜[1] 黄高峰[1] 佟立丽[1] 曹学武[1] 

机构地区：[1]上海交通大学机械与动力工程学院,上海200240

出　　处：《原子能科学技术》2010年第B09期238-241,共4页Atomic Energy Science and Technology

摘　　要：本文选取了直接注入管线破裂始发的严重事故,分析堆芯熔融物压力容器内保持(IVR)策略实施以后压力容器下腔室内堆芯碎片和压力容器下封头的响应、堆芯碎片与压力容器壁面的传热、压力容器外壁面与堆腔水之间的传热以及压力容器不同区域的热流密度。研究表明,该事故序列下未发生下封头蠕变失效,区域4有最早发生蠕变失效的可能性。The severe accident induced by direct vessel injection line break was chosen. The responses for debris in lower plenum and lower head of reactor vessel, heat transfer between debris and reactor vessel wall, heat transfer between cavity water and outer wall of reactor vessel, heat flux of different areas after IVR countermeasure was implemented were analyzed. The results indicate that no creep damage is occurred, and the area 4 is likely to be creep damage earliest.

关 键 词：直接注入管线破裂 严重事故 IVR 

分 类 号：TL364.4[核科学技术—核技术及应用]