反应堆冷却剂环境对690合金传热管疲劳性能影响研究

doi:10.11902/1005.4537.2014.102

中国腐蚀与防护学报

2015, Vol. 35

Issue (3): 213-219 DOI: 10.11902/1005.4537.2014.102

研究报告

本期目录 | 过刊浏览

反应堆冷却剂环境对690合金传热管疲劳性能影响研究

刘晓强¹(

),徐雪莲¹,谭季波²,王媛²,吴欣强²,郑宇礼²,孟凡江¹,韩恩厚²

2. 中国科学院金属研究所中国科学院核用材料与安全评价重点实验室沈阳 110016

Effect of Reactor Coolant Environment on Fatigue Performance of Alloy 690 Steam Generator Tubes

Xiaoqiang LIU¹(

),Xuelian XU¹,Jibo TAN²,Yuan WANG²,Xinqiang WU²,Yuli ZHENG²,Fanjiang MENG¹,En-Hou HAN²

1. Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
2. Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China

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摘要:

针对核电站蒸汽发生器690合金传热管,通过在室温空气、高温空气以及模拟压水堆高温高压水环境下的疲劳性能测试,研究了环境介质对690合金传热管疲劳寿命的影响,并考察了溶解氧和应变速率等的影响规律,探讨了高温高压水环境下690合金传热管的腐蚀疲劳机理。结果表明,690合金传热管具有足够的疲劳设计安全裕度,且压水堆冷却剂环境对690合金传热管的疲劳寿命影响不明显；溶解氧和应变速率对690合金传热管的腐蚀疲劳寿命的影响也不敏感。推测690合金传热管在高温高压水中的腐蚀疲劳过程主要由膜破裂滑移/溶解机制控制。

关键词 ：腐蚀疲劳, 690合金, 传热管, 疲劳设计

Abstract：

The low cycle fatigue behavior of alloy 690 steam generator tubes in three different environments was investigated, i.e. in air at ambient temperature and 325 ℃ respectively as well as in simulated PWR primary water at 325 ℃. Meanwhile, the influence of dissolved oxygen and strain rate on fatigue life was considered. The results show that the design related with the fatigue life for the alloy 690 steam generator tube is very conservative, and the effect of PWR coolant environment is limited; while the corrosion fatigue life of the alloy 690 is not susceptible to the effect of the dissolve oxygen and strain rate under this test condition. Therefore, it is conferred that the corrosion fatigue behavior may be controlled by film rupture slip/dissolution mechanism.

Key words： corrosion fatigue alloy 690 steam generator tube fatigue design

基金资助:大型先进压水堆核电重大专项支撑项目(2010ZX06004-18) 资助

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引用本文:

刘晓强,徐雪莲,谭季波,王媛,吴欣强,郑宇礼,孟凡江,韩恩厚. 反应堆冷却剂环境对690合金传热管疲劳性能影响研究[J]. 中国腐蚀与防护学报, 2015, 35(3): 213-219.
Xiaoqiang LIU, Xuelian XU, Jibo TAN, Yuan WANG, Xinqiang WU, Yuli ZHENG, Fanjiang MENG, En-Hou HAN. Effect of Reactor Coolant Environment on Fatigue Performance of Alloy 690 Steam Generator Tubes. Journal of Chinese Society for Corrosion and protection, 2015, 35(3): 213-219.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2014.102 或 https://www.jcscp.org/CN/Y2015/V35/I3/213

图1 扁舟状试样图

图2 690合金传热管在3种不同环境中的应变范围-疲劳寿命数据

图3 690合金传热管疲劳性能数据与NUREG相关数据[8]对比图

图4 应变速率与溶解氧对690合金传热管高温高压水环境腐蚀疲劳寿命影响

图5 690合金传热管在室温、325 ℃空气和高温高压水中的疲劳裂纹形貌

图6 690合金传热管高温高压水腐蚀疲劳断口的体式形貌

图7 1.0%应变幅条件下疲劳断口表面的SEM像

图8 不同环境条件下疲劳断口表面的EDS分析

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