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作 者:夏祖讽[1] 王明弹[1] 黄小林[1] 王晓雯[1]
出 处:《核动力工程》2002年第A02期123-129,共7页Nuclear Power Engineering
基 金:国防科工委"九五"科研攻关项目
摘 要:通过建立符合先进核电厂安全壳结构特点的线性和非线性有限元分析模型,得出合理的安全壳预应力张拉顺序,计算出安全壳在设计事故内压、严重事故内压状态下的工作性能及其极限承载能力,并与1:10的大比例尺结构模型试验结果相互比较,取得一致的结论:先进核电厂安全壳符合国际上极限承载力≥2.5倍设计内压的合格标准。从而验证了先进核电厂安全壳概念设计的合理性。Several 3D models that simulate the containment in the advanced nuclear power plant (NPP) are established. The thesis achieves some valuable viewpoints about the characteristic of the containment under the inner pressure of design accident and serious accident by linear and non-linear finite element analysis (FEA). The reasonable tensioning sequence of tendons can be arranged. Also the ultimate pressure capacity of containment is worked out. It is greater or equal than two and half the times of inner pressure of design accident. That meets the criterion that is widely accepted all over the world. The result on the scale of 1:10 model experiment confirms it. All of these show that the containment can fully agree with the desires of design, and the conceptive design is reasonable.
关 键 词:百万千瓦级核电厂 安全壳 结构设计 预应力 内压 有限元分析 模型试验
分 类 号:TM623.4[电气工程—电力系统及自动化] TL364.3[核科学技术—核技术及应用]
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