Low-cycle-fatigue behaviour of superalloy blade materials at elevated temperature

Plumbridge, W. J.; Ellison, E. G.

doi:10.1179/mst.1987.3.9.706

Cited by 34 publications

(16 citation statements)

References 19 publications

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“…A greater decrease in cycles to failure at lower strain ranges with increasing hold time was also observed, consistent with the results of Nimonic PE-16, a Ni-Cr superalloy (12). Furthermore, the amount of inelastic strain is relatively similar with increasing hold times, particularly at the 0.6% strain range, as shown in Figures 2 and 3.…”

Section: Discussionsupporting

confidence: 77%

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The Role of Environment on High Temperature Creep-Fatigue Behavior of Alloy 617

Carroll

Cabet

Wright

2010

ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts a and B

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Alloy 617 is the leading candidate material for an intermediate heat exchanger (IHX) application of the Very High Temperature Nuclear Reactor (VHTR), expected to have an outlet temperature as high as 950°C. Acceptance of Alloy 617 in Section III of the ASME Code for nuclear construction requires a detailed understanding of the creep-fatigue behavior. Initial creep-fatigue work on Alloy 617 suggests a more dominant role of environment with increasing temperature and/or hold times evidenced through changes in creep-fatigue crack growth mechanism/s and failure life. Furthermore, previous work on corrosion of nickel base alloys in impure helium has suggested that this environment is far from inert with respect to Alloy 617. Continuous cycle fatigue and creepfatigue testing of Alloy 617 was conducted at 950°C and 0.3% and 0.6% total strain in air to simulate damage modes expected in a VHTR application. Continuous cycle and creep-fatigue specimens exhibited intergranular cracking, but did not show evidence of grain boundary cavitation. Despite the absence of grain boundary cavitation to accelerate crack propagation, the addition of a hold time at peak tensile strain was detrimental to cycle life. This suggests that creep-fatigue interaction may occur by a different mechanism or that the environment may be partially responsible for accelerating failure. INTRODUCTIONThe Next Generation Nuclear Plant (NGNP) being developed in the US is a Very High Temperature Nuclear Reactor (VHTR) with a gas as the primary coolant. Conceptual design requires an outlet temperature of greater than 850°C to efficiently generate hydrogen, with a maximum expected temperature of 950°C. A critical component in the VHTR system is the Intermediate Heat Exchanger (IHX), which will operate at the reactor outlet temperature of up to 950°C.

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Section: Discussionsupporting

confidence: 77%

“…Typically three types of failure are defined: fatigue-dominated, creepdominated, and creep-fatigue interaction. Microstructural schematics of this have been clearly illustrated by Hales (11) and Plumbridge and Ellis (12). A comprehensive summary has been written by Rodrigez and Rao (13).…”

Section: Al Oxidementioning

confidence: 99%

The Role of Environment on High Temperature Creep-Fatigue Behavior of Alloy 617

Carroll

Cabet

Wright

2010

ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts a and B

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show abstract

“…Metallographic analysis revealed that continuously cycled specimens exhibited transgranular cracking, while creep-fatigue specimens cracked intergranularly. Further, these creep-fatigue specimens did not show evidence of creep voids in the form of large round cavities at grain boundaries, as has been described for other alloy systems [4,5]. Instead, populations of fine intergranular cracks were observed in the interiors of the specimens.…”

Section: Introductionmentioning

confidence: 56%

“…The fatigue component is considered to be the initiation and propagation of surface cracks, while the creep component is manifested as creep voids on interior grain boundaries (or wedge cracking at triple junctions), each of which develop independently [3][4][5]. The linking of these two deformation modes results in an accelerated failure [3][4][5]. There has been little work on the specific evolution of each of these two mechanisms during very high temperature creep-fatigue deformation.…”

Section: Introductionmentioning

confidence: 97%

The development of microstructural damage during high temperature creep–fatigue of a nickel alloy

Carroll

Cabet

Carroll

et al. 2013

International Journal of Fatigue

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“…Materials such as, 1Cr-Mo-V [14,15] [24] and Goswami [14] reported compressive dwell sensitivity in 2.25Cr-Mo. In titanium alloys Ti-6Al-4V [25] and IMI 829 [26], and many nickel base alloys [27][28][29] are reported to exhibit compressive dwell sensitivity. The larger compression dwell sensitivity in various alloys systems has been attributed essentially due to various phenomena, such as development of tensile mean stress, shape and size of cavities and oxidation behavior.…”

Section: Effect Of Application Of Hold On Cyclic Stress Response (Csrmentioning

confidence: 99%

Understanding low cycle fatigue and creep–fatigue interaction behavior of 316 L(N) stainless steel weld joint

Shankar

Mariappan

Sandhya

et al. 2016

International Journal of Fatigue

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Low-cycle-fatigue behaviour of superalloy blade materials at elevated temperature

Cited by 34 publications

References 19 publications

The Role of Environment on High Temperature Creep-Fatigue Behavior of Alloy 617

The Role of Environment on High Temperature Creep-Fatigue Behavior of Alloy 617

The development of microstructural damage during high temperature creep–fatigue of a nickel alloy

Understanding low cycle fatigue and creep–fatigue interaction behavior of 316 L(N) stainless steel weld joint

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