Review of R&D for supercritical water cooled reactors

Abstract

The Supercritical Water-Cooled Reactor (SCWR) is a high temperature, high pressure water-cooled reactor that operates above the thermodynamic critical point (374 °C, 22.1 MPa) of water. In general terms, the conceptual designs of SCWRs can be grouped into two main categories: pressure vessel concepts proposed first by Japan and more recently by a Euratom partnership, and pressure tube concepts proposed by Canada, generically called the Canadian SCWR. Other than the specifics of the core design, these concepts have many similar features, like outlet pressure and temperatures, steam cycle options, materials, or heat transfer characteristics. Therefore, the R&D needs for each reactor type are common, which enables collaborative research to be pursued. The paper provides an overview on research and development performed so far on the SCWR within the Generation IV International Forum.