Stress corrosion crack growth rate of welded joint used for low-pressure rotor of nuclear turbine in oxygenated pure water at 180 degrees C

Chu Tongjiao; Cui Haichao; Tang Xinhua; Lu Fenggui

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Stress corrosion crack growth rate of welded joint used for low-pressure rotor of nuclear turbine in oxygenated pure water at 180 degrees C

机译：用于180摄氏度的氧化纯水中核电机低压转子的焊接接头的应力腐蚀裂纹生长速率

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Stress corrosion cracking (SCC) growth behavior of NiCrMoV steels welded joint of nuclear steam turbine was systematically investigated, which was conducted in pure water with 8 ppm oxygen at 180 degrees C. Crack growth rate (CGR) was used to evaluate the susceptibility of SCC for WM with fine bainites and HAZ with coarse prior austenite grains, simultaneously the cracking mechanisms for both zones were explored. WM has lower CGR than HAZ under the similar stress intensity factor, showing it had higher resistance to SCC. Oxygen promoted the nucleation and propagation for cracks. The oxygen diffusion zone (ODZ) formed in front of inner oxide layer through continually diffusion of oxygen in grain, and caused the embrittlement and transgranular cracking for WM. However, fine grains in WM could bear crack driving force and reduce stress concentration to increase the resistance for transgranular crack propagation. As for HAZ, the chromium-rich carbides along the prior austenite grain boundaries (PAGBs) accelerated the intergranular oxidation and facilitated the formation of intergranular oxide zone (IOZ). Thus, the crack could easily propagate in PAGE, and lead to higher CGR for the HAZ. (C) 2019 Elsevier B.V. All rights reserved.

机译：系统研究了Nicrmov钢的应力腐蚀裂解（SCC）生长行为核蒸汽涡轮机的焊接接头，其在纯水中在180℃下用8ppm氧进行，使用裂纹生长速率（CGR）来评估SCC的易感性对于具有细贝氏体和HAZ的WM，具有粗糙的先前奥氏体晶粒，同时探讨了两个区域的开裂机制。在类似的应力强度因子下，WM具有比HAX更低的CGR，表明它具有更高的SCC抗性。氧气促进了裂缝的成核和繁殖。在内氧化物层前面形成的氧气扩散区（ODZ）通过在晶粒中连续地扩散，并导致脆化和转晶裂解用于Wm。然而，WM中的细粒可以承受裂缝驱动力并降低应力集中以增加转晶裂纹繁殖的抗性。至于HAZ，沿前奥氏体晶界（PAGBS）的富含铬的碳化物加速了晶间氧化，促进了晶间氧化物区的形成（IOZ）。因此，裂缝可以在页面中容易地传播，并导致HAZ的更高CGR。（c）2019 Elsevier B.v.保留所有权利。

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来源
《Journal of Nuclear Materials: Materials Aspects of Fission and Fusion》 |2019年第2019期|共15页
作者
Chu Tongjiao; Cui Haichao; Tang Xinhua; Lu Fenggui;
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作者单位

Shanghai Jiao Tong Univ Sch Mat Sci &

Engn Shanghai Key Lab Mat Laser Proc &

Modificat Shanghai 200240 Peoples R China;

Shanghai Jiao Tong Univ Sch Mat Sci &

Engn Shanghai Key Lab Mat Laser Proc &

Modificat Shanghai 200240 Peoples R China;

Shanghai Jiao Tong Univ Sch Mat Sci &

Engn Shanghai Key Lab Mat Laser Proc &

Modificat Shanghai 200240 Peoples R China;

Shanghai Jiao Tong Univ Sch Mat Sci &

Engn Shanghai Key Lab Mat Laser Proc &

Modificat Shanghai 200240 Peoples R China;

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原文格式 PDF
正文语种 eng
中图分类原子能技术;
关键词
Crack growth rate; Internal oxidation; Bainite; Carbide; Intergranular oxide;

机译：裂纹增长率;内部氧化;贝氏体;碳化物;晶间氧化物;

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1. Stress corrosion crack growth rate of welded joint used for low-pressure rotor of nuclear turbine in oxygenated pure water at 180 degrees C [J] . Chu Tongjiao, Cui Haichao, Tang Xinhua, Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2019,第期

机译：用于180摄氏度的氧化纯水中核电机低压转子的焊接接头的应力腐蚀裂纹生长速率
2. Transient and steady state crack growth kinetics for stress corrosion cracking of a cold worked 316L stainless steel in oxygenated pure water at different temperatures [J] . Zhanpeng Lu, Tetsuo Shoji, Yoichi Takeda, Corrosion science . 2008,第2期

机译：316L不锈钢在不同温度下的氧化纯水中的应力腐蚀开裂的瞬态和稳态裂纹扩展动力学
3. Effects of loading mode and water chemistry on stress corrosion crack growth behavior of 316L HAZ and weld metal materials in high temperature pure water [J] . Zhanpeng Lu, Tetsuo Shoji, Yoichi Takeda, Corrosion science . 2008,第3期

机译：加载方式和水化学对高温纯水中316L HAZ和焊接金属材料应力腐蚀裂纹扩展行为的影响
4. EVALUATION, REDESIGN, AND REPAIR OF A NUCLEAR STEAM TURBINE LOW-PRESSURE ROTOR SUFFERING FROM INTERGRANULAR STRESS CORROSION CRACKING [C] . John J. Glover, Alan Beecher, James Beverly 2001 International Joint Power Generation Conference Vol.2 Jun 4-7, 2001, New Orleans, Louisiana . 2001

机译：晶间应力腐蚀开裂的核蒸汽轮机低压转子的评估，重新设计和修复
5. Chloride-Induced Stress Corrosion Cracking in Used Nuclear Fuel Welded Stainless Steel Canisters. [D] . Xie, Yi. 2016

机译：废旧核燃料焊接不锈钢罐中的氯化物引起的应力腐蚀开裂。
6. Hot tensile properties and constant load stress corrosion cracking test data of autogenous weld joints of super 304HCu stainless steel in boiling MgCl2 solution [O] . M. Vinoth Kumar, V. Balasubramanian 2018

机译：沸腾MgCl2溶液中超级304HCu不锈钢自生焊缝的热拉伸性能和恒应力腐蚀开裂试验数据。
7. Pitting Corrosion and Stress Corrosion Cracking around Heat Affected Zone in Welded Joint of CrNiMoV Rotor Steel in Chloridized High Temperature Water [O] . Luo L.H., Huang Y.H., Xuan F.Z. 2015

机译：CrNiMoV转子钢在氯化高温水中焊接接头热影响区周围的点腐蚀和应力腐蚀开裂。
8. Prediction of pure water stress corrosion cracking (PWSCC) in nickel base alloys using crack growth rate models [R] . Thompson, C. D., Krasodomski, H. T., Lewis, N., 1995

机译：用裂纹扩展速率模型预测镍基合金中纯水应力腐蚀开裂（pWsCC）

Stress corrosion crack growth rate of welded joint used for low-pressure rotor of nuclear turbine in oxygenated pure water at 180 degrees C

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