ZHU Guangqiang LIAO Changbin DAI Bing GUI Chun. Fatigue status assessment for reactor pressure vessel based on actual operational transient[J]. Nuclear techniques, 2013, 36(4): 040641
ZHU Guangqiang LIAO Changbin DAI Bing GUI Chun. Fatigue status assessment for reactor pressure vessel based on actual operational transient[J]. Nuclear techniques, 2013, 36(4): 040641 DOI: 10.11889/j.0253-3219.2013.hjs.36.040641.
Background:Fatigue is an important ageing mechanism in RPV and it must be contained to ageing management working range.Purpose:In order to ensure the safety operation of nuclear power plants
as extension of RPV service time
it is necessary to assess the fatigue damage caused by actual operation transient.Methods:Based on monitoring data of actual operation during the past eleven years
refer to design transient
the statistic analysis for types and occurrence times of actual transient is carried out
at the same time
every transients are combined as different operation cycles and the temperature field and stress field of typical components are analyzed by FEM.Results:Based on these information
fatigue analysis and assessment are finished
if later-actual transients are similar with the previous transients
the calculation result shows that the ratio between maximum of cumulative usage factors and design calculation value is 0.4967 the design transients is conservative.Conclusions:Fatigue status of RPV could be assessed and traced quickly through fatigue status assessment method in this paper based on actual operational transient and assessment result would be a good reference for RPV aging management.