首页> 外文会议>ASME Pressure Vessels and Piping conference >APPLICABILITY OF MINIATURE C(T) SPECIMEN TO FRACTURE TOUGHNESS EVALUATION FOR THE IRRADIATED JAPANESE REACTOR PRESSURE VESSEL STEEL
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APPLICABILITY OF MINIATURE C(T) SPECIMEN TO FRACTURE TOUGHNESS EVALUATION FOR THE IRRADIATED JAPANESE REACTOR PRESSURE VESSEL STEEL

机译:微型C(T)试样在辐照日本反应堆压力容器钢断裂韧性评估中的适用性

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Fracture toughness evaluations for irradiated reactor pressure vessel (RPV). steels are essential in the structural integrity assessment of RPVs. In Japanese pressurized water reactor (PWR) plants, fracture toughness tests are conducted for irradiated RPV steels through the surveillance tests and fracture toughness data are obtained. Lately, the Master Curve (MC) approach has become the main stream in fracture toughness evaluation. However, there can be the case that the number of fracture toughness data is not enough for the MC method in some Japanese PWR plants because of limited numbers of fracture toughness specimens contained in the surveillance capsules. On the other hand, for the Japanese PWR plants, a surveillance capsule generally contains a lot of Charpy impact specimens which miniature C(T) (Mini-C(T)) specimens with a size of 4×10×9.6mm can be taken from. Therefore, it is planned that additional fracture toughness tests are performed using Mini-C(T) specimens after the Charpy impact tests to obtain sufficient fracture toughness data for the MC method. Applicability of the Mini-C(T) specimen to the MC evaluation has been studied in a series of international round robin test programs coordinated by Central Research Institute of Electric Power Industry (CRIEPI). In these programs and the related studies, it was demonstrated that the reference temperature (T_0) can be determined by the Mini-C(T) specimens without any specific difficulties for the unirradiated RPV base metals. In addition, CRIEPI has recently reported on the basis of their studies that the fracture toughness tests could be successfully performed on the typical unirradiated RPV weld metal and the valid T_0 can be determined with the data obtained from the weld metal as well as base metals. However, few papers reported applicability of the Mini-C(T) specimen to the MC evaluation for irradiated RPV steels. In this study, fracture toughness tests using Mini-C(T) specimens were conducted on the irradiated Japanese Industrial Standards (JIS) SFVQ1A steel (equivalent to ASME A508 C1.3 steel). The Mini-C(T) specimens were machined out from some broken halves of Charpy impact specimens used in a surveillance test of an actual Japanese PWR plant by a wire cut electric spark machine followed by fatigue precracking. After the fracture toughness tests, the evaluation was performed on the obtained fracture toughness data according to the MC method. The effect of specimen size on T_0 was studied and applicability of the Mini-C(T) specimen was discussed by comparing the existing results of fracture toughness tests using the 1/2T-C(T) specimens conducted in the surveillance test. In addition, the issues to obtain valid T_0 for irradiated materials were discussed.
机译:辐照反应堆压力容器(RPV)的断裂韧性评估。钢在RPV的结构完整性评估中至关重要。在日本的压水堆(PWR)工厂中,通过监视测试对辐照的RPV钢进行了断裂韧性测试,并获得了断裂韧性数据。最近,主曲线(MC)方法已成为断裂韧性评估中的主流。但是,在某些日本PWR工厂中,由于监测胶囊中包含的断裂韧性样品数量有限,可能存在断裂韧性数据的数量不足以使用MC方法进行MC方法的情况。另一方面,对于日本的压水堆工厂,监视舱通常包含许多夏比冲击标本,可以提取尺寸为4×10×9.6mm的微型C(T)(Mini-C(T))标本从。因此,计划在夏比冲击试验后使用Mini-C(T)试样进行额外的断裂韧性试验,以获得足够的MC方法断裂韧性数据。在中央电力工业研究所(CRIEPI)协调的一系列国际循环试验计划中,已经研究了Mini-C(T)样品对MC评估的适用性。在这些程序和相关研究中,证明了可以通过Mini-C(T)样品确定参考温度(T_0),而对于未经辐照的RPV贱金属没有任何特殊困难。另外,CRIEPI最近根据他们的研究报告,可以对典型的未经辐照的RPV焊接金属成功进行断裂韧性测试,并且可以根据从焊接金属以及贱金属获得的数据确定有效的T_0。但是,很少有论文报道了Mini-C(T)样品在辐照RPV钢的MC评估中的适用性。在这项研究中,使用Mini-C(T)试样对受辐照的日本工业标准(JIS)SFVQ1A钢(相当于ASME A508 C1.3钢)进行了断裂韧性测试。 Mini-C(T)样品是由切碎的夏比冲击试样的一半切成的,这些试样是通过线切割电火花机对日本PWR实际工厂进行的监视测试,然后进行疲劳预裂化。在断裂韧性测试之后,根据MC方法对获得的断裂韧性数据进行评估。研究了试样尺寸对T_0的影响,并通过比较在监视试验中使用1 / 2T-C(T)试样的断裂韧性试验的现有结果,讨论了Mini-C(T)试样的适用性。此外,还讨论了获得有效的被辐照材料T_0的问题。

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