HTR-PM反应堆厂房单侧钢板混凝土空心组合屋盖设计研究
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摘要
华能山东石岛湾核电厂高温气冷堆核电示范工程反应堆厂房屋盖系统(长43.8m,宽33.5m,层高16m)采用单侧钢板混凝土(HSC)空心组合结构,模块化制作、安装。结构分析表明,在各种工况和荷载组合下,结构整体及构件强度、变形指标均能满足相关规范要求。静力试验表明,采用《型钢混凝土组合结构技术规程》(JGJ138—2001)计算结构强度及变形是适宜的,结构延性高,模块化制作安装速度快,质量可靠,缩短了HTR-PM示范工程建设安装周期,取得了良好的经济效果。
The half-steel-concrete(HSC) hollow composite structure was used in the reactor building roof system(43. 8 meters long,33. 5 meters wide and 16 meters high) of Hua Neng Shandong Shidaowan nuclear power plant HTR-PM demonstration project. The modular manufacture and installation was used in this structure. The analysis for structure shows that under various conditions and loading combinations,the structural integrity and component strength and deformation index can meet the requirements of the relevant specifications. The static test shows that it is appropriate to use the Technical specification for steel reinforced concrete composite structures(JGJ 138—2001) to calculate the structural strength and deformation. A good ductility performance of this structure was found. Using modular manufacture and installation,with reliable quality,can shorten the construction period of the HTR-PM demonstration project and achieve good economic effect.
The half-steel-concrete(HSC) hollow composite structure was used in the reactor building roof system(43. 8 meters long,33. 5 meters wide and 16 meters high) of Hua Neng Shandong Shidaowan nuclear power plant HTR-PM demonstration project. The modular manufacture and installation was used in this structure. The analysis for structure shows that under various conditions and loading combinations,the structural integrity and component strength and deformation index can meet the requirements of the relevant specifications. The static test shows that it is appropriate to use the Technical specification for steel reinforced concrete composite structures(JGJ 138—2001) to calculate the structural strength and deformation. A good ductility performance of this structure was found. Using modular manufacture and installation,with reliable quality,can shorten the construction period of the HTR-PM demonstration project and achieve good economic effect.
引文
[1]压水堆核电厂核安全有关的混凝土结构设计要求:NB/T 20012—2010[S].北京:国家能源局,2010.
[2]核电厂抗震设计规范:GB 20267—97[S].北京:国家技术监督局、中华人民共和国建设部,1997.
[3]混凝土结构设计规范:GB 50010—2010[S].北京:中国建筑工业出版社,2011.
[4]钢结构设计规范:GB 50017—2003[S].北京:中国计划出版社,2003.
[5]建筑抗震设计规范:GB 50011—2010[S].北京:中国建筑工业出版社,2010.
[6]型钢混凝土组合结构技术规程:JGJ 138—2001[S].北京:中国建筑工业出版社,2001.
[2]核电厂抗震设计规范:GB 20267—97[S].北京:国家技术监督局、中华人民共和国建设部,1997.
[3]混凝土结构设计规范:GB 50010—2010[S].北京:中国建筑工业出版社,2011.
[4]钢结构设计规范:GB 50017—2003[S].北京:中国计划出版社,2003.
[5]建筑抗震设计规范:GB 50011—2010[S].北京:中国建筑工业出版社,2010.
[6]型钢混凝土组合结构技术规程:JGJ 138—2001[S].北京:中国建筑工业出版社,2001.