| 压水堆核电站蒸汽发生器用600合金管在含铅高温碱溶液中的应力腐蚀行为研究 |
| |
| 引用本文： | 但体纯,王俭秋,韩恩厚,柯伟.压水堆核电站蒸汽发生器用600合金管在含铅高温碱溶液中的应力腐蚀行为研究[J].腐蚀科学与防护技术,2008,20(5):313-316. |
| |
| 作者姓名： | 但体纯 王俭秋 韩恩厚 柯伟 |
| |
| 作者单位： | 中国科学院金属研究所,材料环境腐蚀试验研究中心,沈阳,110016 |
| |
| 基金项目： | 国家重点基础研究发展计划(973计划)，中国科学院百人计划经费资助项目 |
| |
| 摘 要： | 采用U型弯曲试样研究了高、低温工厂退火状态的压水堆蒸汽发生器（SG）商用化600合金管在330℃、含10g/L PbO的10%NaOH高温水溶液中的应力腐蚀开裂（SCC）行为.结果表明,在氢浓度很高时，600合金表现为较严重的晶间腐蚀（IGA），最大侵蚀深度约270μm；没有观察到明显的应力腐蚀开裂，腐蚀晶界中有铅的沉积；冷拉预变形、退火温度对材料的腐蚀和应力腐蚀行为的影响不明显.
|
| 关 键 词： | 600合金 应力腐蚀 晶间腐蚀 蒸汽发生器 |
| 收稿时间： | 2008-04-14 |
| 修稿时间： | 2008-05-26 |
STRESS CORROSION CRACKING BEHAVIOR OF ALLOY 600 IN HIGH TEMPERATURE HIGH PRESSURE LEAD-CONTAINING CAUSTIC SOLUTION |
| |
| DAN Ti-chun,WANG Jian-qiu,HAN En-hou,KE Wei.STRESS CORROSION CRACKING BEHAVIOR OF ALLOY 600 IN HIGH TEMPERATURE HIGH PRESSURE LEAD-CONTAINING CAUSTIC SOLUTION[J].Corrosion Science and Protection Technology,2008,20(5):313-316. |
| |
| Authors: | DAN Ti-chun WANG Jian-qiu HAN En-hou KE Wei |
| |
| Affiliation: | Environmental Corrosion Center;Institute of Metal Research;Chinese Academy of Sciences;Shenyang 110016 |
| |
| Abstract: | Stress corrosion cracking(SCC)behavior of commercial mill-annealed (MA) alloy 600 tubing materials used for pressurized water reactors(PWRs)steam generators(SGs)in high-temperature high pressure lead containing caustic solution was investigated by reversed U-bend(RUB)samples.The results indicated that when hydrogen content was high, alloy 600 suffered from serious intergranular attack(IGA),and the observed maximum depth of IGA was about 270 μm;lead was found to deposit at grain boundaries;a pre-strain by cold tension and mill-annealing temperatures did not obviously affect the stress corrosion cracking behavior of alloy 600. |
| |
| Keywords: | 600 alloy stress corrosion cracking(SCC) intergranular attack(IGA) steam generator(SG) |
| 本文献已被 CNKI 维普 万方数据 等数据库收录！ |
| 点击此处可从《腐蚀科学与防护技术》浏览原始摘要信息 |
|
点击此处可从《腐蚀科学与防护技术》下载全文 |
