Japanese activities concerning nuclear codes and standards - Part II

This series of papers has been issued to give general views on recent Japanese activities related to nuclear codes and standards. Part II of the series describes component aging aspects and future trends. The component aging aspects include evaluation methods for vessels based on elastic-plastic fracture mechanics, environmental fatigue evaluation guidelines and inspection and evaluation guidelines for reactor internals. With respect to future trends, the development of the International Thermonuclear Experimental Reactor code and the System-Based Code are introduced.