The fission-powered the supercritical water-cooled nuclear reactor (SCWR) concepts were first explored in the 1950s and early 1960s as it is a Light Water Reactor (LWR), which operates above the thermodynamic critical point of water (374 °C, 22,1 MPa). Later, (SCWR) was considered in the Generation IV International Forum (GIF) as one of the promising advanced concepts of nuclear reactors, addressing the enhanced safety goals and the proliferation and physical protection goals. The main advantages are simplier design and the higher thermal efficiency that also leads to improved economics Plant simplification as a result of single-phase coolant directly coupled to the energy conversion system and therefore no need for steam generators, steam separators, dryers or coolant recirculation pump.
The International Symposium focused on Super-Critical Water-Cooled Reactors (ISSCWRs) was firstly organized in 2000 in Tokyo, Japan. Within followed twenty years, the symposia were realized next to Japan (2003) in China (2007, 2013 and 2017), in Europe (Germany 2009, Finland 2015) and in Canada (2011 and 2019). After the success of previous nine symposia, the 10th ISSCWR will be organized in the heart of Europe – in the Czech Republic – under the auspices of the Research Centre Řež (CVR) and in cooperation with the generation IV International forum (GIF).
The ISSCWR thus traditionally provides a forum for discussion of advances and issues, for sharing information and facilitating technology transfer, and for establishing new as well as for fastening the existing collaborations on SCWR issues between international research organizations across whole the world. Among the main R&D topics of interest belong the reactor core and fuel design, materials and corrosion, chemistry, thermal-hydraulics, passive safety system and balance of plant. The official language of the symposium is English.