Journal article
Materials Assessment for the Canadian SCWR Core Concept
Abstract
As part of the development effort of the Generation IV Forum, Canada has undertaken research to support the conceptual design of a pressure-tube-based supercritical water-cooled reactor (SCWR). With an outlet temperature of 625°C and a coolant pressure of 25 MPa, this concept requires fuel-cladding materials that can sustain very harsh in-core conditions. After reviewing the worldwide efforts in SCWR materials since the 1950s, a materials …
Authors
Zheng W; Guzonas D; Boyle KP; Li J; Xu S
Journal
JOM, Vol. 68, No. 2, pp. 456–462
Publisher
Springer Nature
Publication Date
2 2016
DOI
10.1007/s11837-015-1758-0
ISSN
1047-4838