Transferability of small-specimen data to large-scale component fracture assessment

核反应堆管道组件的完整性对于确保在核电厂寿命期内始终向堆芯供应冷却剂至关重要。证明完整性的输入之一是断裂力学评估，以证明缺陷容限。在英国，R6程序是证明这种缺陷容限的核工业标准。R6包含一个评估方法的层次结构。在确保结构完整性使用更高层次的方法的一个困难是证明的断裂参数确定从试样的应用程序在组件级的可转移性。印度加压重水反应堆（PHWR）的反应堆级管道组件已进行了大量的测试，以提高对可转移性的理解。试验包括直管和弯头，具有各种裂纹和载荷。本项目将使用一系列缺陷评估方法评估这些测试，以证明实际管道组件的可转移性。

The integrity of the piping components of a nuclear reactor is vital to ensure the supply of coolant to the core at all times during the plant life span. One of the inputs to demonstrating integrity is a fracture mechanics assessment to demonstrate defect tolerance. Within the UK, the R6 procedure is the nuclear industry standard for demonstrating such defect tolerance. R6 contains a hierarchy of assessment approaches. A difficulty in ensuring structural integrity using the higher level methods is the demonstration of transferability of fracture parameters determined from specimens to the application at component level. A large number of tests have been performed on reactor grade piping components of the Indian Pressurized Heavy Water Reactor (PHWR) to improve understanding of transferability. The tests consist of straight pipes and elbows, with a variety of cracks and loadings. This project will assess these tests using a range of defect assessment approaches to demonstrate transferability for practical piping components.