Abstract
A number of methods for predicting the creep-fatigue life
of P91 steel are presented and discussed. Beside the
interaction diagram method established in the design
codes, ASME Subsection NH and RCC-MR, and the ductility
exhaustion modification (DE) established in BS-R5, a set
of simpler models are considered. Application of
different rules to creep-fatigue experiments on available
P91 data with relatively short hold times showed that
some of the interaction diagram methods are overly
conservative and predicted extensive creep damage for all
tests. The simplified models showed excellent performance
and the two modified ductility based interaction diagram
models (SMDE and EMDE) performed satisfactorily. The
relative in-sensitivity to the creep deformation rate
displayed by the modified ductility exhaustion models
demonstrate a general advantage of these models against
purely stress-based approach, particularly when
considering the variability of material property and
other uncertainties encountered when assessing actual
components. However, because the creep damage is low in
most tests with fatigue damage dominating and the
expected negative impact of cyclic softening on creep
damage, it is not possible to draw solid conclusions as
to the likely accuracy and conservatism of these models
for increased creep damage during longer dwells that will
likely occur in plant. Also, a thorough description is
given in the application of the RCC-MR and the ASME
Subsection NH codes in the design calculations for Korean
SFR heat exchangers.
Original language | English |
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Place of Publication | Rome |
Publisher | European Commission EC |
Number of pages | 64 |
Publication status | Published - 2014 |
MoE publication type | D4 Published development or research report or study |
Keywords
- creep-fatigue assessment
- modelling
- P91 steel
- nuclear reactors