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首页> 外文会议>ASME Pressure Vessels and Piping Conference >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：铸造不锈钢制成的热老化初级冷却剂管道的断裂行为

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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°C. 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：通过热老化在轻水反应器的工作温度下，通过热老化降低了由双相铸造不锈钢制成的初级冷却剂管道的裂缝韧性，以所谓的低上架反应器压力容器钢。与反应器压力容器相比，初级冷却剂管道超声波检测的裂纹检测能力较差。它建立一个标准程序来评估比例模型一次冷却配管的内表面上的热老化一次冷却剂piping.Crack扩展的结构完整性在四点弯曲试验进行测定是重要的。在325°C时，管道已经老化以模拟60多年的操作。基于管材的测量拉伸性能评价裂缝前部的裂缝延伸力。它们与材料的J_（垫）吻合较好-ΔA使用1TCT试样测定的。歼受控裂纹扩展是verified.Because主冷却剂管道已经小的平均径厚，也不会被压扁与其说照常薄滚边。这意味着如果裂缝处的假想弹性应力是相同的假想弹性应力，则裂缝延伸部小于薄壁管的延伸部。估计裂缝延伸力的另一个点是热老化铸造不锈钢的拉伸性能。预测热老化铸造不锈钢的拉伸性能和断裂韧性的方法尚未提出直到最近。通过施加所提出的性质，通过该研究的测试结果证实是合适的，并且最近关于裂纹检测能力的研究，制备了评估热老化的原发性冷却剂管中裂缝裂缝延伸力的简单方法。将应用于老年日核电站结构完整性分析的评估。

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