Supercritical water-cooled reactor materials - Summary of research and open issues

摘要

The Supercritical Water Reactor (SCWR) is one of the six reactor concepts being investigated under the framework of the Generation Ⅳ International Forum (GIF). Research on materials and chemistry for supercritical water-cooled reactors dates back to the 1960s when a number of reactor concepts using water at supercritical temperatures but sub-critical pressures (nuclear steam) were studied. There is also significant experience available from the operation of supercritical fossil-fired power plants. In this paper, the materials requirements of the various SCWR concepts are introduced, with a focus on the European Union pressure vessel concept and the Canadian pressure tube concept. The current understanding of the key materials degradation issues is reviewed, and knowledge gaps identified.