Journal
PROGRESS IN NUCLEAR ENERGY
Volume 77, Issue -, Pages 282-299Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.pnucene.2014.02.021
Keywords
Conceptual design; Supercritical water; Materials; Heat transfer; Fuel qualification
Categories
Funding
- European Commission as part of their project SCWR-FQT [269908]
- SUSEN Project of the European Regional Development Fund (ERDF) [CZ.1.05/2.1.00/03.0108]
- Natural Resources Canada through the Office of Energy Research and Development
- Atomic Energy of Canada Limited
- Natural Sciences and Engineering Research Council of Canada
- Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT)
Ask authors/readers for more resources
The Supercritical Water-Cooled Reactor (SCWR) is a high temperature, high pressure water-cooled reactor that operates above the thermodynamic critical point (374 degrees 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. (C) 2014 Elsevier Ltd. All rights reserved.
Authors
I am an author on this paper
Click your name to claim this paper and add it to your profile.
Reviews
Recommended
No Data Available