Thermomechanical Fatigue Initiation in Nuclear Grades of Austenitic Stainless Steel Using Plant Realistic Loading

Glenn Trownson, Peter Gill, W. Brayshaw, J. Watson, J. Mann
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Abstract

The effect of a Pressurised Water Reactor (PWR) environment on fatigue life is currently assessed using methods such as NUREG/CR-6909 for initiation and ASME Code Case N809 for crack growth, which may be inherently conservative for certain components, especially when considering plant relevant loading. The thermal shock testing with thick-walled specimens as discussed in this paper allows for more plant relevant loading regimes to be utilised in assessments, incorporating through-wall stress gradients, thick walled test specimens and out-of-phase temperature/strain characteristics. This should lead to improvements in reducing the levels of excess conservatism in current assessment methodologies. The capability of the test facility was first presented in PVP2016-63161 [4]. Since then, significant modifications have been made in order to maximise the achievable strain amplitudes in the thick-walled specimen geometry, alongside minimising typical test durations. This was achieved by maximising the temperature differential between the hot and cold cycles and tuning the cycle length in order to ensure that the cycle is long enough to achieve a target strain amplitude, whilst ensuring that it is not so long as to unreasonably increase test durations. This paper details the results of the thermal shock testing performed to date, the development of accompanying Finite Element Analysis (FEA), preliminary initiation data and the development of the various Non Destructive Testing (NDT) techniques used to detect fatigue crack initiation on the thick-walled specimens. Owing to the long testing times needed to achieve the required cycling, various NDT techniques were developed and employed to confirm the presence of fatigue cracking in the thick-walled test specimens before considering more in-depth characterisation using destructive techniques. Eddy Current Array (ECA) testing has been specifically developed for this testing and uses a 360-degree custom bore probe to conduct non-contact ECA measurements on the inner surface of the test specimens. Calibration blocks containing various sized Electrical Discharge Machining (EDM) notches were used to provide a calibration (amplitude and phase) of eddy current responses for prospective flaw depth sizing from indications. The ECA testing performed has provided indications that fatigue cracking is present within the thick-walled specimens tested and subsequent Visual Testing (VT) was performed to assess the highlighted indications from the ECA testing. The VT methods employed included a video borescope for imaging the inner walls of the specimen. In order to increase the detection capabilities (by improving the contrast) the VT was used in conjunction with fluorescent Dye-Penetrant (fDP) testing, whereby a method was developed for using fDP within the inside bore of the specimen alongside a custom ultraviolet (UV) source to better highlight cracking. This paper discusses the success of the NDT developments and testing performed to date and details the latest complementary crack growth assessment work.
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工厂真实载荷下奥氏体不锈钢核牌号的热机械疲劳引发
压水反应堆(PWR)环境对疲劳寿命的影响目前是用NUREG/CR-6909等方法进行评估的,用ASME规范案例N809来评估裂纹扩展,这对某些部件来说可能本质上是保守的,特别是考虑到与工厂相关的负载。本文中讨论的厚壁试样热冲击试验允许在评估中使用更多与工厂相关的加载制度,包括穿壁应力梯度、厚壁试样和相外温度/应变特性。这应导致在减少目前评估方法中过分保守的程度方面有所改进。该测试设施的能力首次在PVP2016-63161中提出[4]。从那时起,为了最大限度地提高厚壁试样几何形状中可实现的应变幅度,同时最小化典型测试持续时间,已经进行了重大修改。这是通过最大化冷热循环之间的温差和调整循环长度来实现的,以确保循环足够长以达到目标应变幅度,同时确保它不会长到不合理地增加测试持续时间。本文详细介绍了迄今为止进行的热冲击试验的结果、伴随的有限元分析(FEA)的发展、初步的起裂数据以及用于检测厚壁试样疲劳裂纹起裂的各种无损检测(NDT)技术的发展。由于需要很长的测试时间来实现所需的循环,在考虑使用破坏性技术进行更深入的表征之前,开发并采用了各种无损检测技术来确认厚壁试件中疲劳裂纹的存在。涡流阵列(ECA)测试是专门为这种测试开发的,它使用360度定制孔探头在测试样品的内表面进行非接触式ECA测量。校准块包含各种尺寸的电火花加工(EDM)缺口,用于根据指示提供涡流响应的校准(幅度和相位),以预测缺陷深度尺寸。进行的ECA测试提供了疲劳开裂的迹象,在测试的厚壁试样中存在疲劳开裂,随后进行视觉测试(VT)来评估ECA测试中突出的迹象。所采用的VT方法包括用于成像标本内壁的视频管镜。为了提高检测能力(通过提高对比度),VT与荧光染料渗透(fDP)测试结合使用,由此开发了一种方法,在样品的内孔内使用fDP和定制的紫外线(UV)源,以更好地突出裂缝。本文讨论了迄今为止NDT开发和测试的成功,并详细介绍了最新的互补裂纹扩展评估工作。
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