低约束几何对核反应堆压力容器铁素体钢T0测量值的影响

Geena K. Rait, C. Davies, S. Garwood
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摘要

目前评估反应堆压力容器(RPV)铁素体钢断裂韧性的要求可能过于保守,因为材料测试采用了高约束几何形状,如紧绷拉伸(C(T))或单刃缺口弯曲(SEN(B))试样。这些高约束条件并不代表RPV在服役中所经历的实际条件。如果可以降低这种保守性,就有可能对RPV寿命延长进行更合理的预测。在这项研究中,已知的低约束几何形状,单边缘缺口张力,SEN(T),已经与高约束SEN(B)试样一起进行了测试,以便比较两种情况下的测量T0和断裂韧性值。为了测量t应力和计算Q值,也对两种几何形状进行了有限元分析,从而允许对两种几何形状的约束水平进行量化。8个SEN(B)和8个SEN(T)试件,尺寸分别为24 × 254 × 96 mm和20 × 20 × 200 mm。根据ASTM E1921-17a中提出的指导方针,在零下温度下进行测试,尽可能接近T0。与预期的行为相反,SEN(T)样品显示比SEN(B)样品更高(更少负)的T0。本文对产生这些结果的原因进行了探讨。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
The Effect of a Low Constraint Geometry on Measured T0 Values for a Nuclear Reactor Pressure Vessel Ferritic Steel
Current requirements for assessing the fracture toughness of reactor pressure vessel (RPV) ferritic steels are potentially overly conservative due to the employment of high constraint geometries such as compact tension (C(T)) or single edge notch bend, SEN(B), specimens for material testing. These high constraint conditions are not representative of the actual conditions experienced by the RPV in service. If this conservatism could be reduced, more appropriate predictions for RPV lifetime extension could become a possibility. In this study, a known low constraint geometry, single edge notch tension, SEN(T), has been tested alongside the higher constraint SEN(B) specimen in order to compare measured T0 and fracture toughness values for both cases. Finite element analyses have also been conducted for both geometries in order to measure T-stress and calculate Q values thereby allowing quantification of the level of constraint for both geometries. Eight SEN(B) and eight SEN(T) specimens were tested with dimensions 24 × 254 × 96 mm and 20 × 20 × 200 mm, respectively. Testing was conducted at sub-zero temperatures, as close to the T0 as possible, in accordance with the guidelines presented in ASTM E1921-17a. Contrary to expected behaviour the SEN(T) specimen indicated a higher (less negative) T0 then the SEN(B) specimen. The reason for these results are explored in this paper.
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