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首页> 外文会议>ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2006 vol.1: Codes and Standards >FRACTURE BEHAVIOR OF THERMALLY AGED PRIMARY COOLANT PIPING MADE OF CAST STAINLESS STEEL
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FRACTURE BEHAVIOR OF THERMALLY AGED PRIMARY COOLANT PIPING MADE OF CAST STAINLESS STEEL

机译：铸不锈钢热老化的主要冷却剂管道的断裂行为

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摘要

The fracture toughness of primary coolant piping made of duplex cast stainless steel can be reduced by thermal aging, at the operating temperature of a light water reactor, to that of so-called low upper shelf reactor pressure vessel steel. Compared to reactor pressure vessels, the crack detection ability of ultrasonic testing of primary coolant piping is inferior. It is therefore important to establish a standard procedure to assess the structural integrity of thermally aged primary coolant piping.Crack extensions on the inner surface of scale model primary coolant piping were measured in four point bending tests. The piping had been aged to simulate 60 years of operation at 325℃. The crack extension forces at the fronts of cracks were evaluated based on the measured tensile properties of the pipe material. They coincided well with the material's J_(mat)-Δa measured using a 1TCT specimen. The J controlled crack extension was verified.Because the primary coolant piping has small mean radius to thickness, it will not be flattened so much as usual thin piping. It means that the crack extension force is less than that of thin walled pipe if the hypothetical elastic stress at the crack is same. Another point in estimating crack extension force is the tensile properties of thermally aged cast stainless steel. Methods of predicting the tensile properties and fracture toughness of thermally aged cast stainless steel have not been proposed until recently. By applying the proposed properties, which were confirmed to be appropriate by the test results of this study, and a recent study on crack detection ability, a simple procedure for assessing the crack extension force of cracks in thermally aged primary coolant pipe was prepared. It will be applied to the evaluation of structural integrity analyses for aged Japanese nuclear power plants.
机译：通过在轻水反应堆的工作温度下进行热老化，可将由双相铸造不锈钢制成的一次冷却剂管道的断裂韧性降低到所谓的低上层反应堆压力容器钢的断裂韧性。与反应堆压力容器相比，一次冷却剂管道超声检测的裂纹检测能力较差。因此，建立一个标准程序来评估热老化的一次冷却剂管道的结构完整性非常重要。在四点弯曲试验中，对比例模型一次冷却剂管道内表面的裂纹扩展进行了测量。管道已老化以模拟在325℃下运行60年。基于测得的管道材料的拉伸性能，评估了裂纹前端的裂纹扩展力。它们与使用1TCT样品测得的材料的J_（mat）-Δa非常吻合。验证了J控制的裂纹扩展，因为主冷却剂管道的平均半径到厚度较小，因此不会像通常的薄管道那样被压扁。这意味着如果假设在裂纹处的弹性应力相同，则裂纹扩展力小于薄壁管的扩展力。估计裂纹扩展力的另一点是热时效铸造不锈钢的拉伸性能。直到最近，尚未提出预测热时效铸造不锈钢的拉伸性能和断裂韧性的方法。通过应用提出的性能，该性能经本研究的测试结果证实是适当的，并且最近对裂纹检测能力进行了研究，从而制备了一种简单的程序来评估热老化的主冷却剂管道中的裂纹的裂纹扩展力。它将用于评估日本老化核电厂的结构完整性分析。

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