This is Part II of a study on two-bar thermal ratcheting for Alloy 617. The ratcheting strains were evaluated for conditions with the same temperature range but with different mean stresses, heating and cooling rates, time delays, and thermal histories. These testing conditions were designed to be closely aligned to the development of design rules for strain limits at very high temperatures for Alloy 617. These new design rules have been formulated to address the fact that the effects of plastic deformation and creep deformation on the ratcheting strains are not separable at very high temperatures for this alloy.

References

References
1.
Wang
,
Y.
,
Sham
,
T.-L.
, and
Jetter
,
R. I.
,
2014
, “
Two-Bar Thermal Ratcheting for Alloy 617 Part I: Scoping Tests
,”
ASME J. Pressure Vessel Technol.
(in press).10.1115/1.4028302
2.
ASME
,
2013
,
ASME Boiler and Pressure Vessel Code, III, Rules for Construction of Nuclear Facility Components, Division 1, Subsection NH, Class 1, Components in Elevated Temperature Service — 2013 ed.
,
American Society of Mechanical Engineers
,
New York
.
3.
Carter
,
P.
,
Jetter
,
R.
, and
Sham
,
T.-L.
,
2012
, “
Application of Elastic-Perfectly Plastic Cyclic Analysis to Assessment of Creep Strain
,”
ASME
Paper No. PVP2012-78082. 10.1115/PVP2012-78082
4.
Carter
,
P.
,
Jetter
,
R.
, and
Sham
,
T.-L.
,
2012
, “
Application of Shakedown Analysis to Evaluation of Creep-Fatigue Limits
,”
ASME
Paper No. PVP2012-78083. 10.1115/PVP2012-78083
5.
Sartory
,
W.
,
Young
,
H.
,
Battiste
,
R.
, and
Smith
,
J.
,
1977
, “
Thermal Ratcheting Test of 2¼Cr-1Mo Steel to Type 316 Stainless Steel Pipe: Test TTT-3
,” Oak Ridge National Laboratory, Oak Ridge, TN, Technical Report No. ORNL/5330.
6.
Zheng
,
X.
,
Xuang
,
F.
, and
Zhao
,
P.
,
2011
, “
Ratcheting-Creep Interaction of Advanced 9–12% Chromium Ferrite Steel With Anelastic Effect
,”
Int. J. Fatigue
,
33
(
9
), pp.
1286
1291
.10.1016/j.ijfatigue.2011.04.009
7.
Ando
,
M.
,
Isobe
,
N.
,
Kikuchi
,
K.
, and
Enuma
,
Y.
,
2012
, “
Effect of Ratchet Strain on Fatigue and Creep–Fatigue Strength of Mod.9Cr–1Mo Steel
,”
Nucl. Eng. Des.
,
247
, pp.
66
75
.10.1016/j.nucengdes.2012.02.017
8.
Kawashima
,
K.
,
Ishikawa
,
A.
, and
Asada
,
Y.
,
1999
, “
Ratcheting Deformation of Advanced 316 Steel Under Creep–Plasticity Condition
,”
Nucl. Eng. Des.
,
193
(
3
), pp.
327
336
.10.1016/S0029-5493(99)00188-0
9.
Carroll
,
M. C.
, and
Carroll
,
L. J.
,
2013
, “
Developing Dislocation Subgrain Structures and Cyclic Softening During High-Temperature Creep–Fatigue of a Nickel Alloy
,”
Metall. Mater. Trans. A
,
44
(
8
), pp.
3592
3607
.10.1007/s11661-013-1737-4
10.
Carroll
,
L. J.
,
Cabet
,
C.
,
Carroll
,
M. C.
, and
Wright
,
R. N.
,
2013
, “
The Development of Microstructural Damage During High Temperature Creep–Fatigue of a Nickel Alloy
,”
Int. J. Fatigue
,
47
, pp.
115
125
.10.1016/j.ijfatigue.2012.07.016
11.
Wang
,
Y.
,
Sham
,
T.-L.
, and
Jetter
,
R. I.
,
2014
, “
Alloy 617 Creep-Fatigue Damage Evaluation Using Specimens With Strain Redistribution
,”
ASME J. Pressure Vessel Technol.
(in press).10.1115/1.4028054
12.
Swindeman
,
R.
,
Robinson
,
D.
,
Williams
,
B.
, and
Thomas
,
D.
,
1982
, “
Two-Bar Thermal Ratcheting Experiments on 2¼Cr-1Mo Steel
,” Oak Ridge National Laboratory, Oak Ridge, TN, Technical Report No. ORNL/TM-8001.
13.
Corum
,
J. M.
, and
Blass
,
J. J.
,
1991
, “
Rules for Design of Alloy 617 Nuclear Components to Very High Temperatures
,”
Fatigue, Fracture, and Risk-1991
, ASME PVP Vol.
215
, American Society of Mechanical Engineers,
New York
, pp.
147
153
.
14.
Carroll
,
L. J.
,
Cabet
,
C.
, and
Wright
,
R. N.
,
2010
, “
The Role of Environment on High Temperature Creep-Fatigue Behavior of Alloy 617
,”
ASME
Paper No. PVP2010-26126. 10.1115/PVP2010-26126
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