Conference
Corrosion and Stress Corrosion Cracking of UNS S31008 and UNS N08810 Alloys in Supercritical Water
Abstract
Abstract The supercritical water-cooled reactor (SCWR) design requires that fuel core outlet temperature will be up to 650 °C at 25 MPa pressure to achieve optimum thermal efficiency. Selection of suitable fuel cladding materials is a critical issue for SCWR concept design. A number of studies have been conducted over the past years and several top-ranking candidate alloys, including austenitic steels (UNS S31008 and UNS N08810), have been …
Authors
Zeng Y; Li J; Amirkhiz BS; Zheng W; Matchim M; Podlesny M
Pagination
pp. 1-15
Publisher
Association for Materials Protection and Performance (AMPP)
Publication Date
March 15, 2015
DOI
10.5006/c2015-05469
Name of conference
CORROSION 2015