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The assessment of reactor pressure vessel defects allowing for crack tip constraint and its effect on the calculation of the onset of the upper shelf

机译:评估反应堆压力容器缺陷时考虑到裂纹尖端的约束及其对上层架起落计算的影响

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The paper shows how a specialised application of the R6 method could be used to calculate a pressure-temperature failure envelope for postulated defects in a reactor pressure vessel (RPV), making due allowance for the distribution of constraint around the crack front. As such, the technique provides a means of estimating a defect-specific onset of upper shelf temperature (OUST). A material's constraint-based toughness behaviour can be described using separate curves to represent the variations of ductile fracture toughness with constraint and cleavage fracture toughness with constraint and temperature. Armed with such a constraint-based material response, and the calculated variation of constraint with pressure determined at different points along the crack front of a defect, the pressure-temperature failure envelope can be estimated by solving equations inherent in the R6 method. The method is illustrated for a spherical RPV fabricated from ferritic steel, with radius 10m and wall thickness 100 mm, by application to three postulated surface-breaking defects: an extended, circumferential defect; and two semi-elliptical defects. Constraint-based fracture toughness curves can be obtained by applying micro-mechanical models to a series of modified boundary layer Finite Element analyses. For each postulated defect an estimate of the OUST is presented and compared against the value which would be obtained from an assessment of high constraint fracture toughness data. For the 5 mm deep extended, circumferential defect, allowance for loss of constraint resulted in a beneficial shift (i.e. to a lower temperature) in the OUST of about - 18.8℃. For the 5 mm deep by 30 mm long surface breaking, semi-elliptical defect, there was a shift in the OUST of - 17.8℃, a value which did not change appreciably when residual stresses were allowed for. For the 25 mm deep by 150 mm long surface-breaking, semi-elliptical defect, the OUST was shifted by - 19.7℃ without allowance for residual stresses, and by - 18.7℃ allowing for residual stresses. All these values represent significant improvements in the OUST. Because the direction of these shifts in the OUST is opposite to that which would occur due to material degradation by in-service neutron irradiation, it is evident that crack-tip constraint is an important factor that should be taken into account in assessing RPV lifetime.
机译:本文显示了如何使用R6方法的特殊应用来计算反应堆压力容器(RPV)中假定缺陷的压力-温度失效包络,从而为裂纹前沿周围的约束分布提供了适当的余量。这样,该技术提供了一种估计特定缺陷的上架温度(OUST)发作的方法。可以使用单独的曲线来描述材料基于约束的韧性行为,以表示延性断裂韧性随约束的变化以及解理断裂韧性随约束和温度的变化。有了这种基于约束的材料响应,并根据沿缺陷的裂纹前沿在不同点处确定的压力计算出的约束变化,可以通过求解R6方法固有的方程来估算压力-温度失效包络线。通过应用到三个假定的表面断裂缺陷,说明了一种由铁素体钢制成的球形RPV的方法,半径为10m,壁厚为100 mm,这是一种延伸的圆周缺陷;和两个半椭圆形缺陷。通过将微机械模型应用于一系列修改后的边界层有限元分析,可以获得基于约束的断裂韧性曲线。对于每个假定的缺陷,都会给出OUST的估计值,并将其与将从高约束断裂韧性数据评估中获得的值进行比较。对于5mm深的延伸的圆周缺陷,失去约束的余量会导致OUST约-18.8℃的有益变化(即降低到较低的温度)。对于5mm深x 30mm长的表面断裂,半椭圆形缺陷,OUST的变化为-17.8℃,当允许残余应力时,该值没有明显变化。对于25毫米深,150毫米长的表面断裂,半椭圆形缺陷,OUST在不考虑残余应力的情况下移动了-19.7℃,在允许了残余应力的情况下移动了-18.7℃。所有这些值代表了OUST的重大改进。由于OUST中这些位移的方向与在役中子辐照引起的材料降解所导致的方向相反,因此很明显,裂纹尖端约束是评估RPV寿命时应考虑的重要因素。

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