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某核电厂LOCA下预应力混凝土安全壳响应规律初探

孙锋 潘蓉 柴国旱 李亮

原子能科学技术Issue(10):1815-1820,6.
原子能科学技术Issue(10):1815-1820,6.DOI:10.7538/yzk.2015.49.10.1815

某核电厂LOCA下预应力混凝土安全壳响应规律初探

Preliminary Study on Response Law of Prestressed Concrete Containment after LOCA in Certain NPP

孙锋 1潘蓉 1柴国旱 1李亮1

作者信息

  • 1. 环境保护部核与辐射安全中心,北京 100082
  • 折叠

摘要

Abstract

After loss of coolant accident (LOCA ) occurs in nuclear power plant ,the temperature field distribution in prestressed concrete containment (PCC ) is nonlinear significantly . However , the detailed calculation method combining temperature and pressure is not proposed in current PCC design code in China .In this paper ,the finite element model for PCC including prestressed tendons was built by using ANSYS code and the temperature field under LOCA was calculated . The calculation results were compared with the theoretical results ,and the accuracy of the proposed model was veri‐fied .The response law of PCC under high pressure and high temperature was prelimina‐rily analysed ,and the effects of temperature and prestressed tendons on PCC were con‐cluded ,w hich can provide reference to the concrete containment design .

关键词

核电厂/预应力混凝土安全壳/LOCA/温度场/响应规律

Key words

nuclear power plant/prestressed concrete containment/loss of coolant acci-dent/temperature field/response law

分类

建筑与水利

引用本文复制引用

孙锋,潘蓉,柴国旱,李亮..某核电厂LOCA下预应力混凝土安全壳响应规律初探[J].原子能科学技术,2015,(10):1815-1820,6.

基金项目

国家科技重大专项资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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