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应变幅对国产锻造奥氏体不锈钢环境疲劳寿命影响的试验研究
Experimental study on the effect of strain amplitude on environmental fatigue life of domestic forging austenitic stainless steel
- 核技术 2016年39卷第12期 文章编号：120604
- 作者机构：
1.环境保护部核与辐射安全中心 北京 100082
2.中华人民共和国环境保护部 北京 100035
3.中国科学院核用材料与安全评价重点实验室中国科学院金属研究所 沈阳 110016
- 作者简介：
[ "孙海涛, 男, 1979年出生, 2005年于北京理工大学获硕士学位, 研究领域为核电机械设备、材料核安全审评与研究", "SUN Haitao, male, born in1979, graduated from Beijing Institute of Technology with a master's degree in 2005, focusing on safety review and research on nuclear mechanical components and materials" ]
吴欣强, E-mail:xqwu@imr.ac.cn WU Xinqiang, E-mail:xqwu@imr.ac.cn
- 基金信息：
DOI：10.11889/j.0253-3219.2016.hjs.39.120604
中图分类号： TL351.6收稿日期：2016-01-20，
修回日期：2016-10-25，
纸质出版日期：2016-12
- 稿件说明：
移动端阅览
孙海涛, 吕爱林, 付强, 等. 应变幅对国产锻造奥氏体不锈钢环境疲劳寿命影响的试验研究[J]. 核技术, 2016,39(12):120604
Haitao SUN, Ailin LYU, Qiang FU, et al. Experimental study on the effect of strain amplitude on environmental fatigue life of domestic forging austenitic stainless steel[J]. Nuclear techniques, 2016, 39(12): 120604
孙海涛, 吕爱林, 付强, 等. 应变幅对国产锻造奥氏体不锈钢环境疲劳寿命影响的试验研究[J]. 核技术, 2016,39(12):120604 DOI： 10.11889/j.0253-3219.2016.hjs.39.120604.
Haitao SUN, Ailin LYU, Qiang FU, et al. Experimental study on the effect of strain amplitude on environmental fatigue life of domestic forging austenitic stainless steel[J]. Nuclear techniques, 2016, 39(12): 120604 DOI： 10.11889/j.0253-3219.2016.hjs.39.120604.
摘要
为验证模拟压水堆核电站冷却剂服役环境对国产锻造主管道用奥氏体不锈钢疲劳寿命的影响，采用高温高压循环水疲劳测试系统对从产品锻件取样加工后的标准试样进行了低周疲劳试验，分析了试验数据与美国机械工程师学会（American Society of Mechanical Engineers，ASME）规范平均/设计疲劳曲线的关系，获得了应变幅对奥氏体不锈钢环境疲劳寿命的影响规律，并初步评价了ASME规范设计疲劳曲线和环境疲劳修正系数的适合性。
Abstract
Background:
2
Environmental assisted fatigue (EAF) is the important issue in the field of fatigue analysis
assessment and safety regulation of pressurized water reactor nuclear components. Some factors affect fatigue life of materials and related mechanisms.
Purpose:
2
The aim is to verify the influence of simulated pressurized water reactor coolant environment on the fatigue life of domestic forging main coolant pipe made of austenitic stainless steel.
Methods:
2
Fatigue tests were conducted using high-temperature and high-pressure water fatigue testing system
and standard round-bar fatigue specimen made from product forging.
Results:
2
The relationship between test data and American Society of Mechanical Engineers (ASME) code fatigue mean/design curve was analyzed. The effect of strain amplitude on fatigue life of austenitic stainless steel was investigated and the suitability of ASME code fatigue design curve and fatigue life environmental correction factor were preliminarily evaluated.
Conclusion:
2
The fatigue life of forged 316LN stainless steel in high-temperature and high-pressure water are lower than those at room temperature in air. The environmental degradation is more obvious under low strain amplitudes than that under high strain amplitudes. The best-fit curve based on the updated Argonne National Laboratory (ANL) model is recommended for the fatigue design of domestic austenitic stainless steel. The environmental effect should be incorporated into the fatigue design of domestic austenitic stainless steel. The fatigue crack mainly initiated from the surface micro-pits and slip bands for the domestic forged austenitic stainless steel in high-temperature and high-pressure water.
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Keywords
references
孙 海涛 , 王 臣 , 熊 冬庆 , . 压水堆核电站冷却剂环境对核设备材料疲劳寿命的影响 . 核科学与工程 , 2014 . 34 ( 4 ): 482 - 487 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201404009.htm .
Haitao SUN , Chen WANG , Dongqing XIONG , . Effect of PWR coolant environment on the fatigue life of reactor equipment materials . Nuclear Science and Engineering , 2014 . 34 ( 4 ): 482 - 487 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201404009.htm .
RG1.207:Guidelines for evaluating fatigue analyses incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors[S].Washington DC, US:Nuclear Regulatory Commission, 2007
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ASTM E606:Standard practice for strain-controlled fatigue testing[S].West Conshohocken PA:American Society for Testing and Materials, 2012
国家标准化管理委员会.GB/T 15248:金属材料轴向等幅低循环疲劳试验方法[S].北京:中国标准出版社, 2008
Standardization Administration of the People's Republic of China.GB/T 15248:The test method for axial loading constant-amplitude low-cycle fatigue of metallic materials[S].Beijing:Standards Press of China, 2008
ASME:Rules for construction of nuclear facility components[S].New York:American Society of Mechanical Engineers, 2004
徐 松 , 吴 欣强 , 韩 恩厚 , . 核电站用钢的高温高压水腐蚀疲劳研究进展 . 腐蚀科学与防护技术 , 2007 . 19 ( 5 ): 345 - 349 . http://www.cnki.com.cn/Article/CJFDTOTAL-FSFJ200705011.htm .
Song XU , Xinqiang WU , Enhou HAN , . A review of corrosion fatigue of steels for LWR plant high temperature and high pressure water . Corrosion Science and Protection Technology , 2007 . 19 ( 5 ): 345 - 349 . http://www.cnki.com.cn/Article/CJFDTOTAL-FSFJ200705011.htm .
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