“华龙一号”核电厂倒U形预应力钢束摩擦力试验研究  

Experimental Study on Friction Test of Inverted U-Shaped Tendons at HPR1000

作　　者：曹钟引 陈伟 CAO Zhongyin;CHEN Wei(Hainan Nuclear Power Co.,Ltd.,Changjiang,Hainan Prov.572500,China)

机构地区：[1]海南核电有限公司,海南昌江572500

出　　处：《中国核电》2023年第6期798-804,共7页China Nuclear Power

摘　　要：“华龙一号”作为完全自主知识产权当代核电技术,其内层安全壳采用了倒U+水平预应力布置的预应力混凝土结构,在预应力正式施工前为了测试预应力孔道的摩擦力系数与设计数值的吻合度,需要选定特定的钢束通过千斤顶进行逐级拉伸测试其伸长值、拉力值,通过计算得出实际的摩擦系数。设计人员根据试验结果与理论数值的对比,验证和判断预应力孔道的成孔效果,并以此判断是否需要调整设计摩擦系数、张拉力和伸长值等理论数据。作为首堆工程,针对“华龙一号”核电厂倒U形钢束的摩擦力试验结果具有很好代表性和指导性。As a fully independent intellectual property of contemporary nuclear power technology,HPR1000 has been used for the first time in its inverted U-shaped prestressed concrete structure.Before the formal construction of prestressed concrete,in order to test the consistency between the friction coefficient of the prestressed duct and the design value,specific steel tendons need to be selected through jacks for step-by-step tensile testing of their elongation and tension values,and the actual friction coefficient needs to be calculated.Based on the comparison between experimental results and theoretical values,designers verify and judge the pore forming effect of prestressed ducts,and use this to determine whether theoretical data such as design friction coefficient,tensile force,and elongation value need to be adjusted.As the first reactor project,the friction test results for the inverted U-shaped steel beam of the HPR1000 nuclear power plant are very representative and guiding.

关 键 词：“华龙一号” 预应力 摩擦力试验 倒U形钢束 伸长值 

分 类 号：TM623[电气工程—电力系统及自动化]