Publication Type
Conference Paper
Publication Date
Conference Name
2006 ASME Pressure Vessels and Piping Division Conference
Conference Location
Vancouver, Canada
Conference Date
-
Abstract
Mod 9 Cr 1 Mo Steel (grade 91) is one of the materials
envisaged for the Reactor Pressure Vessel of Very High
Temperature Reactors. To avoid the implementation of a
surveillance program covering the monitoring of the creep
damage throughout the whole life of the reactor, it is
recommended to operate the Reactor Pressure Vessel in the
negligible creep regime. In this paper, the background of
negligible creep criteria available in nuclear Codes is first
recalled and their limitations were analyzed. Then, guidance
for deriving criteria more appropriate for mod 9 Cr 1 Mo steel
is provided. Finally, R&D actions in the U. S. and France to
support the new approaches are discussed and recommended.
