Creep-fatigue crack behavior has been investigated for a welded component with 316L stainless steel and Mod. 9Cr–1Mo steel through assessment and test. The evaluation of creep-fatigue crack initiation and propagation was carried out for 316L stainless steel according to the French RCC-MR A16 guide, and the evaluation of creep-fatigue crack initiation for a Mod.9Cr–1Mo steel specimen was carried out with an extended A16 method. A test for a structural specimen with a diameter of 500 mm, height of 440 mm, and thickness of 6.3 mm was performed to compare its results with that by an assessment according to the A16 guide. The specimen was subjected to creep-fatigue loads with 2 h of dwell time at 600°C and various primary loads. The creep-fatigue crack behaviors for the two materials were assessed, observed, and compared. The results showed that the A16 guide for the austenitic stainless steel was fairly conservative for the assessment of creep-fatigue crack initiation while it was reasonably conservative for creep-fatigue crack growth for the present specimen.

1.
Hahn
,
D. -H.
,
Kim
,
Y. -I.
,
Kim
,
S. -O.
,
Lee
,
J. -H.
, and
Lee
,
Y. -B.
, 2007, “KALIMER-600 Conceptual Design Report, KAERI/TR-33811, Korea Atomic Energy Research Institute.
2.
2004, ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, Div. 1, Subsection NH, Class 1 Components in Elevated Temperature Service.
3.
RCC-MR, 2002, Subsection B, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, 2002 Edition, AFCEN.
4.
RCC-MR, 2002, Subsection Z, Technical Appendix 16, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, 2002 Edition, AFCEN.
5.
Metheron
,
Ph.
,
Chapuliot
,
S.
, 2005, “
Fatigue Initiation of Crack Under Mode III and Mixed Mode I+III Loads in a 9Cr Steel
,”
18th International Conference on SMIRT
, Beijing, China, Aug. 7–12, pp.
1896
1903
.
6.
Lee
,
H. -Y.
,
Kim
,
J. -B.
,
Kim
,
S. -H.
, and
Lee
,
J. -H.
, 2006, “
Assessment of Creep-Fatigue Crack Initiation for Welded Cylindrical Structure of Austenitic Stainless Steels
,”
Int. J. Pressure Vessels Piping
0308-0161,
83
, pp.
826
834
.
7.
Lee
,
H. -Y.
,
Lee
,
S. -H.
,
Kim
,
J. -B.
, and
Lee
,
J. -H.
, 2007, “
Creep-Fatigue Damage and Crack Initiation for Mod 9Cr–1Mo Structure With Weldments
,”
ASME PVP 2007/CREEP 8 Conference
, San Antonio, TX, Jul. 22–26.
8.
Lee
,
H. -Y.
,
Lee
,
J. -H.
, and
Kim
,
B. -H.
, 2006, “
Creep-Fatigue Crack Growth Behaviour of a Structure With Crack Like Defects at the Welds
,”
J. Mech. Sci. Technol.
1738-494X,
20
(
12
), pp.
2067
2076
.
9.
2004, ASME Boiler and Pressure Vessel Code, Section II, Materials, Part D Properties, ASME.
10.
Lee
,
H. -Y.
,
Lee
,
S. -H.
,
Kim
,
J. -B.
, and
Lee
,
J. -H.
, 2007, “
Creep-Fatigue Damage for a Structure With Dissimilar Metal Welds of Mod 9Cr–1Mo and 316L Stainless Steel
,”
Int. J. Fatigue
0142-1123,
29
, pp.
1868
1879
.
11.
R5, 2003, Assessment Procedure for the High Temperature Response of Structures, Issue 3, British Energy Generation Ltd.
12.
Lee
,
H. -Y.
, and
Nikbin
,
K. M.
, 2006, “
Modelling the Redistribution of Residual Stresses at Elevated Temperature in Components
,”
J. ASTM Int.
1546-962X,
3
(
1
), pp.
1
15
.
13.
Park
,
J. S.
, 2000, “Standard Procedure of Replication for High Temperature Equipment Life Estimation,” Transactions of the KSME A, 24(9), pp. 2381–2386.
14.
2007, ABAQUS Users Manual, Version 6.6, H.K.S.
15.
Drubay
,
B.
, 2003, “
A16: Guide for Defect Assessment at Elevated Temperature
,”
Int. J. Pressure Vessels Piping
0308-0161,
80
, pp.
499
516
.
16.
Ancelet
,
O.
, and
Chapuliot
,
S.
, 2007, “
Mechanical Behaviour of HTR Materials: Developments in Support of Defect Assessment, Structural Integrity and Lifetime Evaluation
,”
Proceedings of ICAPP 2007
, Nice, France, May 13–18, Paper No. 7182.
17.
RCC-MR, 2002, Subsection Z Technical Appendix A3, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, 2002 Edition.
You do not currently have access to this content.