BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2

P. Arffman, J. Lydman, N. Hytönen, Z. Que, S. Lindqvist
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Abstract

Project BRUTE has investigated weld materials extracted from the decommissioned Barsebäck 2 reactor pressure vessel. The materials investigated originate from the pressure vessel head (RPVH) and beltline regions. The performed mechanical testing include tensile, Charpy impact and fracture toughness testing. Tensile testing with miniature specimens demonstrates a difference of over 50 MPa in the yield and ultimate tensile strengths of the RPVH and beltline materials. Beltline specimens tested at the operating temperature exhibit discontinuity past the yield region, possibly indicating dynamic strain aging. Charpy impact tests were performed around the transition region of the material. Transition curves were fitted, and reference temperatures T28J of −85 °C and −106 °C were determined for RPVH and beltline materials, respectively. This indicates better material properties at beltline compared to the RPVH, in agreement with tensile results. The reference temperatures T28J were further utilized to estimate brittle fracture initiation toughness reference temperatures T0. Fracture toughness testing follows the Master Curve methodology defined in ASTM standard E1921. Reference temperatures T0 were determined at −115.1 °C and −101.1 °C for the RPVH and beltline, respectively, but the tests indicate inhomogeneity in both materials. The mean reference temperatures of the multimodal models TM were determined at −110.0 °C and −96.5 °C, and the associated, margin adjusted lower confidence bounds TM5%, MA at −13.3 °C and −53.0 °C for the RPVH and beltline materials, respectively. The latter values indicate that the inhomogeneity is more extensive in the RPVH. The estimates obtained from the Charpy impact toughness results do not correlate consistently with the fracture toughness-based transition temperature, possibly due to the inhomogeneity of the materials. The results show that the safety of the materials can be assessed reliably, provided that contemporary methods, equipment and analyses are used.
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BRUTE:真实反应堆压力容器材料力学性能的评估来自Barsebäck
BRUTE项目研究了从退役的Barsebäck 2反应堆压力容器中提取的焊接材料。所调查的材料来自压力容器头部(RPVH)和腰带区域。所进行的力学测试包括拉伸、夏比冲击和断裂韧性测试。微型试样的拉伸试验表明,RPVH和腰线材料的屈服强度和极限拉伸强度相差超过50 MPa。在工作温度下测试的腰线试样在屈服区域后表现出不连续,可能表明动态应变老化。在材料的过渡区域周围进行夏比冲击试验。拟合过渡曲线,确定RPVH和腰带材料的参考温度T28J分别为- 85°C和- 106°C。这表明与RPVH相比,腰线处的材料性能更好,与拉伸结果一致。进一步利用参考温度T28J来估算脆性断裂起裂韧性参考温度T0。断裂韧性测试遵循ASTM标准E1921中定义的主曲线方法。RPVH和腰带的参考温度分别为- 115.1°C和- 101.1°C,但测试表明两种材料的不均匀性。多模态模型的平均参考温度TM分别为- 110.0°C和- 96.5°C, RPVH和腰带材料的相关边际调整下置信区间TM5%, MA分别为- 13.3°C和- 53.0°C。后者的数值表明RPVH的不均匀性更为广泛。从Charpy冲击韧性结果中得到的估计与基于断裂韧性的转变温度不一致,可能是由于材料的不均匀性。结果表明,只要采用现代的方法、设备和分析方法,就可以可靠地评估材料的安全性。
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