Fracture Toughness Evaluation of Heat-Affected Zone Under Weld Overlay Cladding in Reactor Pressure Vessel Steel

Y. Ha, T. Tobita, H. Takamizawa, S. Hanawa, Y. Nishiyama
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引用次数: 1

Abstract

An evaluation of the fracture toughness of the heat-affected zone (HAZ), which is located under the weld overlay cladding of a reactor pressure vessel (RPV), was performed. Considering inhomogeneous microstructures of the HAZ, 0.4T-C(T) specimens were manufactured from the cladding strips locations, and Mini-C(T) specimens were fabricated from the distanced location as well as under the cladding. The reference temperature (To) of specimens that were aligned with the middle section of a cladding strip (HAZMCS) was ∼12°C higher than that of specimens that were aligned with cladding strips at the overlap (HAZOCS). To values of partial area in the HAZ were obtained using Mini-C(T) specimen. The To values obtained near the side of the cladding were ∼13°C higher than those away from the cladding. To values of HAZ for both 0.4T-C(T) and Mini-C(T) specimens were significantly lower than that of the base metal at a quarter thickness by 40°C–60°C. Compared to the literature data that indicated fracture toughness at the surface without overlay cladding and base metal of a quarter thickness in a pressure vessel plate, this study concluded that the welding thermal history showed no significant effect on the fracture toughness of the inner surface of RPV steel.
反应堆压力容器钢焊缝覆盖层热影响区断裂韧性评价
对反应堆压力容器(RPV)焊缝覆盖层下热影响区(HAZ)的断裂韧性进行了评价。考虑到热影响区组织的不均匀性,在包层带材处制备0.4T-C(T)试样,在包层带材处制备Mini-C(T)试样。与包层带中部对齐的样品(HAZMCS)的参考温度(To)比在重叠处与包层带对齐的样品(HAZOCS)高~ 12℃。采用Mini-C(T)试样获得热影响区局部面积的To值。在包层侧面附近获得的To值比远离包层的高~ 13°C。0.4T-C(T)和Mini-C(T)试样的HAZ值均显著低于母材四分之一厚度时的40°C - 60°C。对比文献中压力容器板无覆层和母材厚度为1 / 4表面断裂韧性的数据,本研究得出焊接热历史对RPV钢内表面断裂韧性的影响不显著。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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