1-5 of 5
Keywords: SCWR
Close
Follow your search
Access your saved searches in your account

Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031107.
Paper No: NERS-22-1007
Published Online: May 25, 2022
...German Cota-Sanchez; Lin Xiao; Stephane Rousseau Inconel 625 is considered one of the candidate materials for fuel cladding in the Canadian supercritical water reactor. Gas tungsten arc welding (GTAW) is being evaluated as a joining technique for SCWR fuel cladding since this method is widely used...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.
Paper No: NERS-21-1082
Published Online: March 15, 2022
...Y. Dubyk; V. Filonov; Y. Filonova; O. Kovalenko The analysis of deteriorated heat transfer (DHT) influence on the stress–strain state of a perspective core of small modular reactors with supercritical water (SMR SCWR) fuel assemblies is carried out based on experimental and numerical data...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011005.
Paper No: NERS-17-1064
Published Online: January 24, 2019
...J. S. Bell; P. K. Chan; A. Prudil Thorium-based fuel cycles can improve fuel sustainability within the nuclear power industry. The Canadian supercritical water-cooled reactor (SCWR) concept uses this path to achieve the sustainability requirement of the Gen-IV Forum. The study of thorium dioxide...
Journal Articles
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011014.
Paper No: NERS-15-1040
Published Online: December 9, 2015
..., there are a large number of potential problems that must be addressed, particularly the fuel assembly design of the SCWR. SCWRs are a kind of high-temperature, high-pressure, water-cooled reactor that operates above the thermodynamic critical point of water (374°C, 22.1 MPa). Corrosion and degradation of materials...
Journal Articles
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021008.
Published Online: March 24, 2015
... International Forum (GIF) Program has narrowed design options of the nuclear reactors to six concepts, one of which is supercritical water-cooled reactor (SCWR). Among the Generation IV nuclear-reactor concepts, only SCWRs use water as a coolant. The SCWR concept is considered to be an evolution of water-cooled...