Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme

Abstract

The reactor pressure vessel (RPV) is the most critical component of every nuclear power plant (NPP) and continuous evaluation of its mechanical properties is a necessity for long and safe operation. Standard tests require a collection of large-dimension samples coming from the precious and archive materials, usually produced as control segments. Since SPT testing samples are quite small, high activity of irradiated materials is no longer an issue. The SPT technique therefore represents a very useful and effective method applied for characterization of mechanical properties such as ultimate tensile strength (Rm), yield strength (Re), and fracture appearance transition temperature (FATT). Monitoring of structural components in nuclear power plants receives much attention, particularly, in the context of long term operation (LTO) of current plants where the amount of material available for destructive testing is considerably limited.

Mechanics of the small punch test: a review and qualification of additive manufacturing materials

“…The study of the evolution of irradiated materials, being of high interest for development of the SPT in general, was one of the main driving influences for studying the relationship between conventional Charpy and SPT tests and led to the development of the correlation still in use and recommended in the current and upcoming guiding documentation [30,44,49]. Today the study of irradiated materials via SPT still continues to be of high interest to researchers [139][140][141][142].…”