Conference
Advances in materials evaluation for the Canadian SCWR core concept
Abstract
Canada has, since 2007, undertaken research to develop a conceptual design of a pressure-tube based supercritical water-cooled reactor (SCWR). With an outlet temperature of 625 degree C and a coolant pressure of 25 MPa, this concept requires fuel-cladding materials that can sustain high-temperature and high-pressure in-core conditions. An overview of the key aspects of the design related to in-core materials and the recent development of …
Authors
Zheng W; Guzonas D; Boyle KP; Zeng Y; Li J; Greenwood M; Kuyucak S; Xu S
Publication Date
January 1, 2016
Conference proceedings
36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role