Negligible creep conditions for mod 9CR1MO steel

Bernard Riou, Claude Escaravage, Robert W. Swindeman, Weiju Ren, Marie Thérèse Cabrillat, Lucien Allais

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

4 Scopus citations

Abstract

Mod 9CrlMo 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 analyzed. Then, guidance for deriving criteria more appropriate for mod 9CrlMo steel is provided. Finally, R&D actions in the U. S. and France to support the new approaches are discussed and recommended.

Original languageEnglish
Title of host publicationProceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community
DOIs
StatePublished - 2006
EventASME PVP2006/ICPVT-11 Conference - Vancouver, BC, Canada
Duration: Jul 23 2006Jul 27 2006

Publication series

NameAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume2006
ISSN (Print)0277-027X

Conference

ConferenceASME PVP2006/ICPVT-11 Conference
Country/TerritoryCanada
CityVancouver, BC
Period07/23/0607/27/06

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