第三代核电站华龙一号反应堆厂房大体积混凝土温度应力模拟  

THERMAL STRESS SIMULATION OF BLOCK CONCRETE FOR HUALONG 1 REACTOR BUILDING OF THE THIRD GENERATION NUCLEAR POWER PLANT

作　　者：张忠[1] 向群 耿秀伟 刘洪力 程敦旵 岳红波[1] 汪洋[1] 姚辉[1] 

机构地区：[1]中冶建筑研究总院有限公司,北京100088 [2]中国核工业华兴建设有限公司,南京210019 [3]中核集团中国中原对外工程有限公司,北京100191

出　　处：《工业建筑》2016年第10期39-42,186,共5页Industrial Construction

摘　　要：华龙一号核电站是中国自主研发的第三代核电技术,其安全壳混凝土的强度对结构自身强度和公众安全具有重大的意义,作为屏蔽结构重要部件之一的厂房基础不仅承担着支承结构的功能,而且是防止核泄露的重要环节,其对混凝土抗裂要求更高。华龙一号基础采用的多层段合并整体浇筑施工技术对缩短核电工期具有重要的意义,但大体积混凝土施工中的抗裂技术需要进一步研究。基于第三代核电站反应堆厂房大体积混凝土基础施工,通过开展科学分层、优化结构设计,很好地控制了大体积混凝土施工裂缝的发生和开展。The Hualong 1 reactor is the third generation China＇s own research and development nuclear power plant,whose containment has higher requirements for the strength of the structure itself and public safety. The base slab is one of the most important structures supporting and shielding part to nuclear power plants,so the construction quality should be controlled more strictly. The base slab is very larger,so the much more complicated temperature stress occurred during concreting should be studied further. It was carried out scientific layering,optimizing structure,designing better technical measures to control cracks in construction throught the temperature stress analysis.

关 键 词：温度应力 大体积混凝土 反应堆厂房 华龙一号 第三代核电站 

分 类 号：TU755[建筑科学—建筑技术科学]