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Failure Behavior of Internally Pressurized Flawed and Unflawed Steam Generator Tubing at High Temperatures: Experiments and Comparison with Model Predictions

机译：内部加压有缺陷和无瑕蒸汽发生器管道在高温下的失效行为：实验与模型预测的比较

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This report summarizes experimental work performed at Argonne National Laboratory on the failure of internally pressurized steam generator tubing at high temperatures (> or = 700 deg C). A model was developed for predicted failure of flawed and unflawed steam generator tubes under internal pressure and temperature histories postulated to occur during severe accidents. The model was validated by failure tests on specimens with part-through-wall axial and circumferential flaws of various lengths and depths, conducted under various constant and ramped internal pressure and temperature conditions. The failure temperatures predicted by the model for two temperature and pressure histories, calculated for severe accidents initiated by a station blackout, agree very well with tests performed on both flawed and unflawed specimens.

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Majumdar, S.; Shack, W. J.; Diercks, D. R.; Mruk, K.; Franklin, J.; Knoblich, L.;
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年度 1998
页码 1-104
总页数 104
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Steam generators ; Nuclear power plants ; High temperature tests ; Reactor accidents ; Failures ; Cracks ; Creep;

机译：蒸汽发生器;核电站;高温测试;反应堆事故;故障;裂缝;蠕变;

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1. Acceptance criterion for probabilistic structural integrity assessment: Prediction of the failure pressure of steam generator tubing with fretting flaws [J] . Xinjian Duan, Min Wang, Michael Kozluk Nuclear Engineering and Design . 2015,第jana期

机译：概率结构完整性评估的验收标准：带有微动缺陷的蒸汽发生器管道的失效压力预测
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. Experiment and Verification Test of the Once-through Steam Generator of the 10 MW High-temperature Gas-cooled Reactor Flow Stability of the Once-through Steam Generator [J] . Huaiming JU, Yu YU, Zhiyong HUANG, Journal of nuclear science and technology . 2004,第4期

机译：10 MW高温气冷堆直流蒸汽发生器直流稳定性实验及验证试验
4. The in-situ scratching repassivation behavior of steam generator tube material in high-temperature pressurized water [C] . En-hou HAN European corrosion congress . 2016

机译：高温高压水中蒸汽发生管材料的原位刮擦钝化行为
5. Modeling the differential eddy current probe for steam generator tubing inspections using Z parameters [D] . Nguyen, Quang Huy. 1993

机译：使用Z参数对蒸汽发生器管检查的差分涡流探头进行建模
6. Experiments on Temperature Changes of Microbolometer under Blackbody Radiation and Predictions Using Thermal Modeling by COMSOL Multiphysics Simulator [O] . Yu-Zhen Deng, Shiang-Feng Tang, Hong-Yuan Zeng, 2018

机译：利用COMSOL Multiphysics Simulator进行热建模的微辐射热计在黑体辐射和预测下的温度变化实验
7. Failure behavior of internally pressurized flawed and unflawed steam generator tubing at high temperatures -- Experiments and comparison with model predictions [O] . Majumdar, S., Shack, W. J., Diercks, D. R., 1998

机译：内部加压有缺陷和无瑕疵的蒸汽发生器管道在高温下的失效行为 - 实验和与模型预测的比较

Failure Behavior of Internally Pressurized Flawed and Unflawed Steam Generator Tubing at High Temperatures: Experiments and Comparison with Model Predictions

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