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中国核动力研究设计院 核反应堆系统设计技术重点实验室 成都 610213
Received:26 November 2015,
Revised:18 February 2016,
Accepted:2016-02-18,
Published:25 April 2016
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Linyuan KUANG, Liangang ZHENG, Dongchuan SU, et al. A fast approach for fatigue life estimation of structure with pit defect[J]. Nuclear techniques, 2016, 39(4): 040606
Linyuan KUANG, Liangang ZHENG, Dongchuan SU, et al. A fast approach for fatigue life estimation of structure with pit defect[J]. Nuclear techniques, 2016, 39(4): 040606 DOI: 10.11889/j.0253-3219.2016.hjs.39.040606.
基于Miner线性累积损伤理论
探讨了含凹坑缺陷结构使用系数与相应的无缺陷结构使用系数之间的计算关系。在
S
-
N
曲线数据拟合的基础上
推导了许用循环次数的比值计算式
并以核压力容器常用材料为例
给出了计算式待定常数的取值及适用范围。形成的疲劳寿命估算方法
为含凹坑缺陷结构的快速疲劳分析及评定提供了一种参考方法。
Background:
2
The appearance of smooth pit defect brings considerable difficulties to the prediction of fatigue life of structure whilst the traditional approach of fatigue analysis hardly meets the requirements of engineering applications.
Purpose:
2
This study aims to find a fast approach for fatigue life estimation of structure with pit defeat for engineering applications.
Methods:
2
Based on Miner linear cumulative damage rule
the quantitative relation between usage factor of structure with pit defect and that of structure without pit defect is determined. Based on the data fitting of the
S
-
N
curve
the expressions of ratio of the permissible number of cycles are deduced
and the range of application is given for common materials of nuclear pressure vessel.
Results:
2
Computional results using above mentioned approach provide the codomain of undetermined constants and sphere of application.
Conclusion:
2
The approach for fatigue life estimation of structure with pit defect meets the requirements of engineering applications
thus is suitable to fast estimation of fatigue life for nuclear pressure vessel.
余 寿文 , 冯 西桥 . 损伤力学 . 北京:清华大学出版社 , 1997 .
YU Shouwen , FENG Xiqiao . Damage mechanics . Beijing:Tsinghua University Press , 1997 .
ASME Boiler & Pressure Vessel Code . Rules for construction of nuclear facility components . Section Ⅲ Division 1, New York , 2004 .
RCC-M . Nuclear island components . Section I, AFCEN , 2000 .
国家能源局 . 含缺陷核承压设备完整性评定:NB/T 20013-2010 . 北京:原子能出版社 , 2011 .
National Energy Administration . Structural integrity assessment for nuclear pressure-retaining components containing defects:NB/T 20013-2010 . Beijing:Atomic Energy Press , 2011 .
中华人民共和国国家质量监督检验检疫总局 . 在用含缺陷压力容器安全评定:GB/T 19624-2004 . 北京:中国标准出版社 , 2004 .
General Administration of Quality Supervision , Inspection and Quarantine of the People's Republic of China . Safety assessment for in-service pressure vessels containing defects:GB/T 19624-2004 . Beijing:Standards Press of China , 2004 .
陈 传尧 . 疲劳与断裂 . 武汉:华中科技大学出版社 , 2002 .
CHEN Chuanyao . Fatigue and fracture . Wuhan:Huazhong University of Science and Technology Press , 2002 .
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