Multi-State Physics Based Aging Assessment of PWR Steam Generator Tubes Rupture in Case of Primary Water Stress Corrosion Cracking

Askin Guler; Tunc Aldemir; Richard Denning

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Multi-State Physics Based Aging Assessment of PWR Steam Generator Tubes Rupture in Case of Primary Water Stress Corrosion Cracking

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

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The results of this study indicate that a semi-Markov model provides a feasible approach to the evaluation of SGTR probability as an input for the PRA.

机译：这项研究的结果表明，半马尔可夫模型提供了一种可行的方法来评估SGTR概率，作为PRA的输入。

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来源
《Transactions of the American nuclear society》 |2014年第11期|104-106|共3页
作者
Askin Guler; Tunc Aldemir; Richard Denning;
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The Ohio State University 201 West 19th Avenue Columbus, OH 43210-1142;

The Ohio State University 201 West 19th Avenue Columbus, OH 43210-1142;

The Ohio State University 201 West 19th Avenue Columbus, OH 43210-1142;

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1. Effect of shot peening on primary water stress corrosion cracking of Alloy 600 steam generator tubes in an operating PWR plant [J] . Do Haeng Hur, Myung Sik Choi, Deok Hyun Lee, Nuclear Engineering and Design . 2004,第2期

机译：喷丸处理对PWR装置运行中的600合金蒸汽发生器管的一次水应力腐蚀开裂的影响
2. Primary water stress corrosion cracking behaviors in the shot-peened Alloy 600 TT steam generator tubings [J] . In-Gyu Park Nuclear Engineering and Design . 2002,第1a3期

机译：喷丸合金600 TT蒸汽发生器管道中的主要水应力腐蚀开裂行为
3. Stress Corrosion Cracking (SCC) of Nickel-base Weld Metals in PWR Primary Water [J] . Ru Xiong, Yingjie Qiao, Guiliang Liu Materials science forum . 2013,第期

机译：压水堆一次水中镍基焊接金属的应力腐蚀开裂（SCC）
4. Mechanism-based Ageing Management of Primary Water Stress Corrosion Cracking of Ni-base Components in PWR Environments [C] . Tae Hyun Lee, Il Soon Hwang ICAPP 2008;International conference on advances in nuclear power plants . 2008

机译：压水堆环境中镍基成分一次水应力腐蚀开裂的基于机理的时效管理
5. Transient Analysis of the NuScale Power Helical-Coil Steam Generator Tube Rupture Using RELAP5-3D [D] . Johnson, Kyle P. 2021

机译：采用RELAP5-3D对NUSCALE电源螺旋线圈蒸汽发生器管破裂的瞬态分析
6. Stress Corrosion Behaviors of 316LN Stainless Steel in a Simulated PWR Primary Water Environment [O] . Yong Huang, Weisong Wu, Shuo Cong, 2018

机译：316LN不锈钢在模拟压水堆原水环境中的应力腐蚀行为
7. Evaluation of Nondestructive Evaluation Size Measurement for Integrity Assessment of Axial Outside Diameter Stress Corrosion Cracking in Steam Generator Tubes [O] . Kyung-Mun Joo, Jun-Hee Hong 2015

机译：蒸汽发生器管轴向外径应力腐蚀裂缝的完整性评价的非破坏性评价测量评价
8. Intergranular Stress-Corrosion Cracking of Ni-Cr-Fe Alloy 600 Tubes in PWR Primary Water - Review and Assessment for Model Development. Final Report [R] . Garud, Y. S., Gerber, T. L. 1983

机译：压水堆原水中Ni-Cr-Fe合金600管的晶间应力 - 腐蚀开裂 - 模型开发的回顾与评价。总结报告

Multi-State Physics Based Aging Assessment of PWR Steam Generator Tubes Rupture in Case of Primary Water Stress Corrosion Cracking

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