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首页> 外文会议>12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors 2005 vol.2 >CRACK INITIATION IN ALLOY 600 SG TUBING IN ELEVATED PH PWR PRIMARY WATER
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CRACK INITIATION IN ALLOY 600 SG TUBING IN ELEVATED PH PWR PRIMARY WATER

机译：PH压水堆原水中600 SG合金管的裂纹萌生

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Crack initiation tests were carried out using steam generator tubing specimens to evaluate the effect of primary water pH on the tendency for stress corrosion crack initiation. All exposures were in 325℃ water with lithium and boron concentrations selected to simulate at-temperature pH values of 6.9, 7.2 and 7.4. In each environment, a series of eight successive fuel cycles was simulated by approximately 1000-hour exposure cycles. In each of the eight exposure cycles, the Li and B concentrations were "stepped down" in a series of six steps to simulate the boron and lithium changes that occur during a fuel cycle while the dissolved hydrogen concentration was maintained within the range 28-42 cm~3/kg H_2O. The eight heats of tubing used in these tests included several heats of mill annealed Alloy 600 with known low resistance to PWSCC, in addition to thermally treated Alloy 600 and a single heat of thermally treated Alloy 690. All tests were periodically interrupted to examine the RUBs for indications of crack initiation. Total test durations extended to 9736 hours. Analysis of the results in terms of the cumulative number of specimens cracked vs. exposure time in each of the environments was done using Weibull statistics. For each set of data the Weibull characteristic life (η) and the Weibull shape factor (β) were determined. Weibull plots were developed for each test material for which crack initiation was observed. The shortest PWSCC initiation times were consistently observed in the pH 7.2 environment. The longest initiation times were observed in the pH 6.9 solution. The pH 7.4 test results were generally intermediate between the pH 6.9 and pH 7.2 results.
机译：使用蒸汽发生器管道样品进行了裂纹萌生测试，以评估一次水的pH值对应力腐蚀裂纹萌生趋势的影响。所有暴露都在325℃水中，锂和硼的浓度被选择为模拟6.9、7.2和7.4的常温pH值。在每个环境中，通过大约1000小时的暴露循环来模拟一系列八个连续的燃料循环。在八个暴露循环的每个循环中，Li和B的浓度按一系列六个步骤“降低”，以模拟在燃料循环期间发生的硼和锂变化，同时将溶解的氢浓度保持在28-42范围内。 cm〜3 / kg H_2O。这些测试中使用的八种管材热量，除了经过热处理的合金600和经过热处理的合金690的单次加热外，还包括对PWSCC已知具有低电阻的轧制退火合金600的几热。定期中断所有测试以检查RUB用于指示裂纹萌生。总测试时间延长到9736小时。使用Weibull统计数据，根据每种环境下破裂的标本的累积数量与暴露时间的关系，对结果进行了分析。对于每组数据，确定了威布尔特征寿命（η）和威布尔形状因子（β）。针对观察到裂纹萌生的每种测试材料绘制了威布尔图。在pH 7.2环境中始终观察到最短的PWSCC引发时间。在pH 6.9溶液中观察到最长的引发时间。 pH 7.4测试结果通常介于pH 6.9和pH 7.2结果之间。

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