Conference
Filling the gaps in SCWR materials research: Advanced nuclear corrosion research facilities in Hamilton
Abstract
Research efforts on materials selection and development in support of the design of supercritical water-cooled reactors (SCWRs) have produced a considerable amount of data on corrosion, creep and other related properties. Summaries of the data on corrosion [1] and stress corrosion cracking [2] have recently been produced. As research on the SCWR advances, gaps and limitations in the published data are being identified. In terms of corrosion …
Authors
Krausher JL; Zheng W; Li J; Guzonas D; Botton G
Volume
2
Pagination
pp. 837-846
Publication Date
December 1, 2011
Conference proceedings
Canadian Nuclear Society 32nd Annual Conference of the Canadian Nuclear Society and 35th CNS can Student Conference 2011