Plasma-facing components (PFCs) usually need to withstand extreme incident heat flux conditions in nuclear fusion engineering. In situ measurements of deformation to fatigue failure of PFCs under high heat flux (HHF) tests are significant and essential to understand their thermal-mechanical behaviors under servicing conditions; these measurements can provide first-hand and important information for evaluating and optimizing design performance and manufacturing techniques. However, unlike traditional contact measurements with strain gauges, the contactless optical measurement technique is rarely applied to measure or monitor the deformation to fatigue damage process of PFCs employed in HHF tests. In this work, a comprehensive HHF experimental platform was established by combining an electron gun scanning HHF heating system with a three-dimensional digital image correlation (3D-DIC) measurement system based on a vacuum chamber and specially designed optical windows and light sources. The 3D-DIC technology was utilized to measure the field deformation of a divertor mockup under cyclic HHF loads. Validation and qualification tests were conducted on the comprehensive experimental platform to ensure the performance of the platform and the accuracy of the 3D-DIC method. The thermal-induced field deformation of a flat-type divertor mockup under the conditions of 1000 HHF cycles at 10 MW m−2 and 300 HHF cycles at 20 MW m−2 using the 3D-DIC technique was then measured. The mechanical behavior of the accumulated plastic strain and fatigue debonding failure of the W/Cu interface due to periodic thermal stress were captured in situ by the measured strain curves and contours for the first time during HHF tests. The results demonstrate the feasibility and accuracy of the 3D-DIC technique for in situ fatigue deformation and damage strain measurements of PFCs during HHF tests. The proposed methods and technologies are expected to be applied to measure and monitor the servicing performance of PFCs under servicing conditions.
High heat flux tests of mock-ups for ITER divertor application