Tungsten is used as a plasma facing material in many fusion devices for its high melting temperature, low sputtering threshold and low activation. The aim of this project is to understand damage mechanisms in tungsten samples that have been removed from the JET tokamak during the ITER-like Wall campaigns (which included a beryllium main chamber and a tungsten divertor). These samples have been exposed to simultaneous particle and heat loads in a real fusion environment, uniquely positioning them to directly answer questions for future devices such as ITER. Techniques including SEM, EBSD, EDX, TEM, EELS and nanoindentation have been used to look for changes in microstructure and mechanical properties which have occurred during deuterium plasma exposure. The results show the types of damage structures that form as a result of using a beryllium first wall and highlight the importance of assessing a component’s condition before installation in a fusion environment.
