Prediction of materials damage history from stress corrosion cracking in boiling water reactors
Prediction of materials damage history from stress corrosion cracking in boiling water reactors
复制标题
沸水反应堆应力腐蚀开裂材料损伤历史的预测
DOI：
10.1115/1.556148
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发表时间：
2000
期刊：
影响因子：
--
通讯作者：
R. Kilian
中科院分区：
文献类型：
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作者：
I. Balachov;D. Macdonald;B. Stellwag;N. Henzel;R. Kilian
在过去的十年中，我们开发了确定性模型，用于预测沸水堆 (BWR) 主冷却剂回路中应力腐蚀开裂 (SCC) 造成的材料损坏。这些稳态模型已应用于反应器运行的固定状态点，以产生电化学腐蚀电位（ECP）和裂纹扩展速率（CGR）预测。然而，损坏是累积的，因此在任何给定时间预测损坏程度必须整合工厂历史上的裂纹扩展速率。在本文中，我们描述了使用 REMAIN 代码来预测采用内部冷却剂泵的典型沸水堆的冷却剂回路中主要部件的累积损坏函数。例如，向给水中添加相对少量的氢气（例如 0.5 ppm）对 0.197 英寸的损坏发展的影响。分析了位于内部泵出口处的（0.5 厘米）晶间裂纹。据预测，给水中添加氢气将有效抑制裂纹的进一步扩展。我们还首次报告了可变功率工作循环中 SCC 损坏累积的预测。我们预测，氢水化学（HWC）的好处（如恒定环境条件下单个裂纹的行为所表明的那样）会因反应堆功率的变化而显着减弱。
Over the past decade, we have developed deterministic models for predicting materials damage due to stress corrosion cracking (SCC) in boiling water reactor (BWR) primary coolant circuits. These steady-state models have been applied to fixed state points of reactor operation to yield electrochemical corrosion potential (ECP) and crack growth rate (CGR) predictions. However, damage is cumulative, so that prediction of the extent of damage at any given time must integrate crack growth rate over the history of the plant. In this paper, we describe the use of the REMAIN code to predict the accumulated damage functions for major components in the coolant circuit of a typical BWR that employs internal coolant pumps. As an example, the effect of relatively small amounts of hydrogen added to the feedwater (e.g., 0.5 ppm) on the development of damage from a 0.197-in. (0.5-cm) intergranular crack located at the exit of an internal pump was analyzed. It is predicted that hydrogen additions to the feedwater will effectively suppress further growth of the crack. We also report the first predictions of the accumulation of damage from SCC for a variable power operating cycle. We predict that the benefits of hydrogen water chemistry (HWC), as indicated by the behavior of a single crack under constant environmental conditions, are significantly muted by changes in reactor power.