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Effect of cladding on the stress intensity factors in the reactor pressure vessel

机译:熔覆对反应堆压力容器应力强度因子的影响

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摘要

In general, reactor pressure vessels (RPV) are cladded with stainless steel to prevent corrosion and radiation embrittlement. The ASME Sec. XI specifies that a subclad crack which may be found during the in-service inspection must be considered as a semi-elliptical surface crack when the thickness of cladding is less than 40/100 of the crack depth. in order to refine the fracture assessment procedures for such subclad cracks, three-dimensional finite element analyses were applied for various subclad cracks embedded in the base metal. A total of 18 crack geometries were analyzed, and the results were compared with those for idealized semi-elliptical surface cracks for two different loading conditions, i.e. internal pressure and pressurized thermal shock. The resulting stress intensity factors for subclad cracks were 50-70/100, less than those for idealized surface cracks. It has been proven that the condition specified on the ASME Sec. XI is overly conservative for subclad cracks which are assumed to be surface cracks.
机译:通常,反应堆压力容器(RPV)覆盖有不锈钢以防止腐蚀和辐射脆化。 ASME秒XI规定,当包层厚度小于裂纹深度的40/100时,在使用中检查时可能发现的子包层裂纹应被视为半椭圆形表面裂纹。为了完善此类包层裂纹的断裂评估程序,对嵌入在母材中的各种包层裂纹进行了三维有限元分析。总共分析了18种裂纹几何形状,并将结果与​​理想的半椭圆形表面裂纹在两种不同的载荷条件(即内压和加压热冲击)下的结果进行了比较。包层裂纹的应力强度因子为50-70 / 100,小于理想表面裂纹的应力强度因子。已经证明,ASME Sec中规定的条件。对于被认为是表面裂纹的包层裂纹,XI过于保守。

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