核电厂中的结构力学问题
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摘要
结合秦山核电厂一期工程和巴基斯坦CHASNUPP核电厂的设计和建造,着重介绍了上海核工程研究设计院在核电厂结构力学领域的主要研究工作。对于安全壳部分的结构力学问题,考虑了基岩和软土地基两种不同的情况,对于后者仔细研究了土和结构的相互作用。对于设备和管道的结构力学问题,研究了三维应力和三维断裂。结构动力学问题研究了包括流致振动、地震和失水事故的结构响应分析。管道部分着重介绍了破前漏技术的应用。文内介绍了大量的数学模型,采用的计算机程序,分析计算和试验结果,是对压水堆核电厂中的结构力学问题较完整的论述。
The main research works in structural mechanics in reactor technology are emphatically introduced. It is completed by structural mechanics engineers at Shanghai Nuclear Research and Design Institute associated with the design and construction problems for Qianshan NPP Unit 1 and Pakistani CHASNUPP. About structural mechanics problem for the containment, the rock and soft soil two different bases are considered. For the later the interaction between soil and structure is carefully studied. About the structural mechanics problem for the equipment and pipings, the three dimensional stress and fracture analyses are studied. For the structural dynamics problem, including flow induced vibration, the response analyses under earthquake and loss coolant accident loadings are studied. For pipings, the leak before break technique has been emphatically introduced. A lot of mathematical models, the used computer codes, analytical calculations and experimental results are also introduced. This is a comprehensive description about structural mechanics problem in pressurized water reactor nuclear power plant.
The main research works in structural mechanics in reactor technology are emphatically introduced. It is completed by structural mechanics engineers at Shanghai Nuclear Research and Design Institute associated with the design and construction problems for Qianshan NPP Unit 1 and Pakistani CHASNUPP. About structural mechanics problem for the containment, the rock and soft soil two different bases are considered. For the later the interaction between soil and structure is carefully studied. About the structural mechanics problem for the equipment and pipings, the three dimensional stress and fracture analyses are studied. For the structural dynamics problem, including flow induced vibration, the response analyses under earthquake and loss coolant accident loadings are studied. For pipings, the leak before break technique has been emphatically introduced. A lot of mathematical models, the used computer codes, analytical calculations and experimental results are also introduced. This is a comprehensive description about structural mechanics problem in pressurized water reactor nuclear power plant.
引文
1 夏祖讽等.秦山电厂预应力混凝土安全壳的结构研究和设计.CNIC-00714,SNERDI-0019
2 夏祖讽.核电站建在非岩性地基上分析研究.上海核工程研究设计院,1993,(12)
3 ASME Boiler and Pressure Vessel Code Section Ⅲ, Division 2(ACI-359) , 1989
4 韩良弼.核岛主设备中的结构力学问题.上海力学,1989,(4) :62～70
5 NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, U. S Nuclear Regulatory Commission, Chapter 3, 1981
6 ASME Boiler and Pressure Vessel Code Section Ⅲ, Division 1, Subsection NB, NC and ND, 1989
7 曲家棣,徐定耿等.30万千瓦核电站压水堆压力容器的应力分析和试验.核科学与工程,1982,2(4) :289～299
8 曲家棣.反应堆压力容器疲劳分析综述与疲劳估算.第八届全国反应堆结构力学会议论文汇编(第一册),1994,154～159
9 徐定耿等.核电站蒸汽发生器一次侧整体及管板三维有限元应力分析.CNIC-00267,SNERDI-0008
10 王柏松等.核容器接管区开孔区曲率影响区断裂分析与试验。CNIC-00772,SNERDI-0022
11 王伯松,徐定耿.核容器球接管内壁角裂缝应力强度因子三维有限元计算及工程应用。第八届全国反应堆结构力学会议论文汇编,1994,125～130
12 姚伟达等.反应堆吊篮水流振动研究和分析,核科学与工程,1989,9(1)
13 王玉芬,姜南燕.秦山核电厂堆内构件非线性抗震计算.第六届全国反应堆结构力学会议论文汇编,1990,155～158
14 韩良弼等.主设备在事故工况下的动态响应分析.CNIC-00825,SNERDI-0023
15 韩良弼等.蒸汽发生器模拟管束的地震响应分析和试验.CNIC-00828,SNERDI-0024
16 韩良弼.核承压设备应力分析计算机程序能力的描述.核电工程与技术。1994,(4) :30～35
17 高文道.LBB及其在PC工程中的应用.第八届全国反应堆结构力学会议论文汇编,1994,312～318
2 夏祖讽.核电站建在非岩性地基上分析研究.上海核工程研究设计院,1993,(12)
3 ASME Boiler and Pressure Vessel Code Section Ⅲ, Division 2(ACI-359) , 1989
4 韩良弼.核岛主设备中的结构力学问题.上海力学,1989,(4) :62～70
5 NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, U. S Nuclear Regulatory Commission, Chapter 3, 1981
6 ASME Boiler and Pressure Vessel Code Section Ⅲ, Division 1, Subsection NB, NC and ND, 1989
7 曲家棣,徐定耿等.30万千瓦核电站压水堆压力容器的应力分析和试验.核科学与工程,1982,2(4) :289～299
8 曲家棣.反应堆压力容器疲劳分析综述与疲劳估算.第八届全国反应堆结构力学会议论文汇编(第一册),1994,154～159
9 徐定耿等.核电站蒸汽发生器一次侧整体及管板三维有限元应力分析.CNIC-00267,SNERDI-0008
10 王柏松等.核容器接管区开孔区曲率影响区断裂分析与试验。CNIC-00772,SNERDI-0022
11 王伯松,徐定耿.核容器球接管内壁角裂缝应力强度因子三维有限元计算及工程应用。第八届全国反应堆结构力学会议论文汇编,1994,125～130
12 姚伟达等.反应堆吊篮水流振动研究和分析,核科学与工程,1989,9(1)
13 王玉芬,姜南燕.秦山核电厂堆内构件非线性抗震计算.第六届全国反应堆结构力学会议论文汇编,1990,155～158
14 韩良弼等.主设备在事故工况下的动态响应分析.CNIC-00825,SNERDI-0023
15 韩良弼等.蒸汽发生器模拟管束的地震响应分析和试验.CNIC-00828,SNERDI-0024
16 韩良弼.核承压设备应力分析计算机程序能力的描述.核电工程与技术。1994,(4) :30～35
17 高文道.LBB及其在PC工程中的应用.第八届全国反应堆结构力学会议论文汇编,1994,312～318
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