摘要
针对压水堆预应力混凝土安全壳结构设计,中国国家能源局标准NB/T 20303《压水堆核电厂预应力混凝土安全壳设计规范》、美国标准ACI 359《锅炉和压力容器规范》、法国标准RCC-CW《压水堆核相关土建结构设计和建造标准》均给出详细的设计要求。中、美、法安全壳设计规范关于安全壳的设计总体目标、功能要求、设计方法、荷载和荷载组合等要求基本一致,但针对安全壳结构设计的应力、应变限值要求有一定的差异。安全壳设计基准下的结构正常使用和承载能力水平是否一致,难以做出判断。研究分析了中、美、法安全壳设计标准关于安全壳结构应力、应变限值要求的差异,并给出了相关建议。
For the design of pressurized water reactor containment structure,Chinese code NB/T 20303,American code ACI 359,and French code RCC-CW all provide detailed design requirements. The overall objectives,functional requirements,design method,load and load combination requirements of these codes are basically similar.However,the stress and strain limits for containment structure design have certain differences. It is difficult to determine if they have approximately consistent level of containment design capacity in normal service and structure bearing. The paper analyzed the differences on stress and strain limits requirements among Chinese code,American code,and French code,some relevant suggestions were also proposed.
作者
黎鹏飞
LI Pengfei(China Nuclear Power Design Co.Ltd(Shenzhen),Shenzhen 518172,China)
出处
《工业建筑》
CSCD
北大核心
2018年第8期86-91,共6页
Industrial Construction
关键词
预应力混凝土安全壳
应力、应变限值
次应力
裂缝控制
prestressed concrete containment
stress and strain limit
secondary stress
crack control