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Validation of failure and leak rate correlations for stress corrosion cracks in steam generator tubes.

机译：验证蒸汽发生器管中应力腐蚀裂纹的失效和泄漏率相关性。

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Majumdar, S.; Bakhtiari, S.; Kasza, K.; Park, J. Y.;
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年度 2002
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1. Laboratorial technique for fabrication of outer diameter stress corrosion cracking on steam generator tubing [J] . Jae-Min Lee, Sung-Woo Kim, Seong-Sik Hwang, Corrosion Science and Technology . 2014,第3期

机译：在蒸汽发生器管道上制造外径应力腐蚀裂纹的实验室技术
2. Multi-State Physics Based Aging Assessment of PWR Steam Generator Tubes Rupture in Case of Primary Water Stress Corrosion Cracking [J] . Askin Guler, Tunc Aldemir, Richard Denning Transactions of the American nuclear society . 2014,第nova期

机译：一次水应力腐蚀破裂情况下基于PWR蒸汽发生器管破裂的多状态物理老化评估
3. Stress corrosion cracking resistance of materials for steam generator tubing [J] . Paintindia Group Paintindia . 2014,第8期

机译：蒸汽发生器管道材料的抗应力腐蚀开裂性能
4. FAILURE PRESSURE AND LEAK RATE OF STEAM GENERATOR TUBES WITH STRESS CORROSION CRACKS [C] . International conference on nuclear engineering . 2002

机译：压力腐蚀裂纹蒸汽发生器管的故障压力和泄漏率
5. Stress corrosion cracking and internal oxidation of alloy 600 in high temperature hydrogenated steam and water [D] . Lindsay, John. 2015

机译：高温氢化蒸汽和水中合金600的应力腐蚀开裂和内部氧化
6. Corrosion Product Film-Induced Stress Facilitates Stress Corrosion Cracking [O] . Wenwen Wang, Zhiliang Zhang, Xuechong Ren, -1

机译：腐蚀产物膜引起的应力促进应力腐蚀开裂
7. Growth Model of Circumferential Outer Diameter Stress Corrosion Crack in Retired Steam Generator Tube of Kori 1 Nuclear Power Plant [O] . Dong-jin Kim, Hong Pyo Kim, Joung Soo Kim, 2015

机译：Kori 1核电厂退役蒸汽发生器管周向外径应力腐蚀裂纹扩展模型

Validation of failure and leak rate correlations for stress corrosion cracks in steam generator tubes.

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