Abstract

In the code for nuclear equipment, the elasto-plastic correction factor KE is a correction factor when the stress range exceeds the yield limit for simplified elasto-plastic fatigue analysis. The parameters and expressions of KE for commonly used materials (such as austenitic stainless steel) are given in the RCC-M and ASME codes, but the parameters of KE for titanium alloy materials are lacking. Based on the cyclic elasto-plastic constitutive model of Z2CND18.12 (nitrogen control) and KE parameters of austenitic stainless steel given in the code, considering various sensitive factors, a numerical calculation method for determining KE correlation coefficient is established. The elasto-plastic constitutive model of TA16 alloy with nonlinear kinematic hardening was established by the uniaxial tension, strain, and stress cycling tests of TA16 titanium alloy. Based on the numerical calculation method of KE and the constitutive model of TA16 titanium alloy, the expression and correlation coefficient of KE for TA16 titanium alloy were determined.

References

1.
ASME,
2010
, “
ASME Boiler and Pressure Vessel Code Section III: Division 1 Subsection NB: Class 1 Components. Rules for Construction of Nuclear Power Plant Components
,”
The American Society of Mechanical Engineers,
New York.
2.
Afcen
,
2007
, “
RCC-M Code: Section I: Subsection B: Class 1 Components: Design and Construction Rules for Mechanical Components of PWR Nuclear Islands
,”
Afcen
, Paris, France.
3.
ASME
,
2010
, “
ASME Boiler & Pressure Vessel Code: Case N-779: Alternative Rules for Simplified Elastic Plastic Analysis. Class 1, Section III, Division 1
,”
The American Society of Mechanical Engineers
, New York.
4.
Lang
,
H.
,
Rudolph
,
J.
, and
Ziegler
,
R.
,
2011
, “
Performance Study of KE Factors in Simplified Elastic Plastic Fatigue Analyses With Emphasis on Thermal Cyclic Loading
,”
Int. J. Pressure Vessel Piping
,
88
(
8–9
), pp.
330
347
.10.1016/j.ijpvp.2011.06.008
5.
Hubel
,
H.
,
1995
,
Simplified Elasto-Plastic Fatigue Analysis of Smooth Structures
,
European Commission
, Brussels, Belgium.
6.
Xiaolong
,
F. U.
, and
Donghui
,
W. A. N. G.
,
2017
, “
Plastic Correction in Simplified Elasto-Plastic Fatigue Analysis of Nuclear Components
,”
Mech. Eng.
,
1
(
1
), pp.
67
70
.
7.
Slagis
,
G. C.
,
2006
, “
Meaning of KE in Design-by-Analysis Fatigue Evaluation
,”
ASME J. Pressure Vessel Technol.
,
128
(
1
), pp.
8
16
.10.1115/1.2140798
8.
Kan
,
Q. H.
,
Guo
,
S. J.
,
Li
,
J.
,
Kang
,
G. Z.
, and
Yan
,
W. Y.
,
2016
, “
Numerical Investigation on Plastic Strain Correction Factor in Simplified Elasto-Plastic Fatigue Analysis
,”
Appl. Mech. Mater.
,
853
, pp.
226
230
.10.4028/www.scientific.net/AMM.853.226
You do not currently have access to this content.