Abstract

Super-Critical Water-cooled Reactor (SCWR) is one of six advanced nuclear reactor systems selected by GIF for joint R&D. Key technology areas in materials, chemistry, thermal-hydraulics, safety, neutronics and fuel development are being investigated by GIF participants and several IAEA member states. The International Symposium on SCWRs is aimed at providing a forum for discussion of advancements and issues, sharing information and technology transfer, and establishing future collaborations on research and developments for SCWRs between international research organizations. CNS is hosting the 9th International Symposium on SCWRs (ISSCWR-9) in cooperation with the Generation-IV International Forum and the International Atomic Energy Agency. ISSCWR-9 is of interest to those involved in SCWR core design, fuel design, materials, chemistry, corrosion, thermal-hydraulics, safety analyses and co-generation. The official language of the Symposium is English.