The effect of environment on high-temperature hold time fatigue behavior of annealed 2.25 pct Cr 1 pct Mo steel

Hecht, R. L.; Weertman, J.

doi:10.1007/s11661-998-0039-8

Cited by 20 publications

(4 citation statements)

References 14 publications

(28 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…41 Now, 2.25Cr1MoV has greatly substituted the former, because its strength and resistance against hydrogen attack at elevated temperature are greatly improved after an addition of vanadium. 42 The low-cycle fatigue and creep-fatigue interaction of annealed ferrite 2.25Cr1Mo steel have been widely investigated by Brinkman et al, 43 Jaske, 44 Challenger and Vining, 45 and Hecht et al 46,47 since 1970s. They found that fatigue lives with compressed hold were shorter than with tensile hold for ferrite 2.25Cr1Mo steel, because compressed hold resulted in the more damaging tensile mean stress and circumferential cracks with cycling.…”

Section: Introductionmentioning

confidence: 99%

Ratcheting‐fatigue behaviour of bainite 2.25Cr1MoV steel with tensile and compressed hold loading at 455°C

Zhao

Chen

et al. 2019

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

The ratcheting behaviour of a bainite 2.25Cr1MoV steel was studied with various hold periods at 455°C. Particular attention was paid to the effect of stress hold on whole‐life ratcheting deformation, fatigue life, and failure mechanism. Results indicate that longer peak hold periods stimulate a faster accumulation of ratcheting strain by contribution of creep strain, while double hold at peak and valley stress has an even stronger influence. Creep strains produced in peak and valley hold periods are noticeable and result in higher cyclic strain amplitudes. Dimples and acquired defects are found in failed specimen by microstructure observation, and their number and size increase under creep‐fatigue loading. Enlarged cyclic strain amplitude and material deterioration caused by creep lead to fatigue life reduction under creep‐fatigue loading. A life prediction model suitable for asymmetric cycling is proposed based on the linear damage summation rule.

show abstract

Section: Introductionmentioning

confidence: 99%

Ratcheting‐fatigue behaviour of bainite 2.25Cr1MoV steel with tensile and compressed hold loading at 455°C

Zhao

Chen

et al. 2019

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

show abstract

“…Therefore, the higher cyclic stress response is caused by the higher strain hardening, which is induced by the higher stain amplitude. Additionally, higher cyclic stress is also the reason that compressive holding time is negative for the lifetime, which has been achieved by Hecht et al 33 To better characterize the effect of strain amplitude and holding time, softening ratio is proposed. Geometry of the welded groove, complexity of the microstructure, and different crack propagation behaviour are accounted for the difference.…”

Section: Evolution Of Cyclic Stressmentioning

confidence: 99%

“…During compressive holding time, compressive creep strain is introduced, and as a result, material bears larger inelastic strain during tensile part of each cycle in comparison with the continuous LCF, accordingly, higher cyclic stress response is achieved for longer compressive holding time. Additionally, higher cyclic stress is also the reason that compressive holding time is negative for the lifetime, which has been achieved by Hecht et al 33 To better characterize the effect of strain amplitude and holding time, softening ratio is proposed. It is defined as the ratio of peak stress reduction in the middle lifetime to the peak stress in the first cycle.…”

Section: Evolution Of Cyclic Stressmentioning

confidence: 99%

Experimental and numerical characterization of low cycle fatigue and creep fatigue behaviour of P92 steel welded joint

Wang

Zhang

Gong

et al. 2017

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

Low cycle fatigue (LCF) and creep fatigue interaction (CFI) behaviour of P92 steel welded joint were investigated experimentally and numerically. Strain‐controlled LCF tests at different strain amplitudes and CFI tests at different peak strain holding time were conducted. Evolutions of cyclic stress response, mean stress, and creep strain during cycling were described, in which the influence of strain amplitude and holding time were investigated. A specific heat treatment process was proposed to get the homogenous simulated material of fine grain region and coarse grain region in the heat affected zone. Material parameters of parent material, fine grain heat affected zone, coarse grain heat affected zone, and weld metal in the unified viscoplasticity model were then determined and validated. To predict the LCF and CFI behaviour of welded joint, 3‐dimensional unified viscoplasticity model with a modified isotropic variable was compiled into ABAQUS UMAT. The comparison between the predicted and experimental result under LCF and CFI loadings showed that the simulation results were reasonable and agreed with the experimental data well.

show abstract

“…Notched specimens were also tested. Hecht and Weertman (1998) reported the creep-fatigue data for 2.25Cr-1Mo steel at 500 and 600°C in air or in vacuum. Tests were carried out using hourglass-shaped specimens in uniaxial total strain control.…”

Section: Resolution Of Qualification Issues For Existing Structural Mmentioning

confidence: 99%

Resolution of qualification issues for existing structural materials.

Natesan¹,

Li²,

Majumdar³

et al. 2012

View full text Add to dashboard Cite

This report gives a detailed assessment of several key technical issues that needs resolution for the existing structural materials with emphasis on application in liquid metal reactors (LMRs), in particular, sodium cooled fast reactors. The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for the Advanced Fuel Cycle Initiative (AFCI) Reactor Campaign. The report is the second deliverable in FY09 (M2505050201) under the work package "Advanced Materials Code Qualification".The overall objective of the Advanced Materials Code Qualification project is to evaluate the key technical requirements for the qualification of currently available and future advanced materials for application in sodium reactor systems and the resolution of issues that the U.S. Nuclear Regulatory Commission (NRC) has raised in the past on structural materials in support of the design and licensing of the LMR. Advanced materials are a critical element in the development of sodium reactor technologies. Enhanced materials performance not only improves safety margins and provides design flexibility, but also is essential for the economics of future advanced sodium reactors. Qualification and licensing of advanced materials are prominent needs for developing and implementing advanced sodium reactor technologies. However, the development of sufficient database and qualification of these materials for application in LMRs require considerable amount of time and resources. In the meantime, the currently available materials will be used in the early development of fast reactors.Nuclear structural component designs in the U.S. comply with the ASME Boiler and Pressure Vessel Code Section III (Rules for Construction of Nuclear Facility Components) and the NRC grants licensing. As the LMR will operate at higher temperatures than the current light water reactors (LWRs), the design of elevated-temperature components must comply with ASME Section III Subsection NH (Class 1 Components in Elevated Temperature Service). Assessment of materials performance issues and high temperature design methodology issues pertinent to the LMR were presented in an earlier report (Natesan et al. 2008). In a subsequent report ), we addressed the needs in high temperature methodologies for design of various high temperature components in sodium cooled fast reactor.The present report addresses several key technical issues for the currently available structural materials such as Type 304 and 316 austenitic stainless steels and ferritic steels such as 2.25Cr-1Mo and modified 9Cr-1Mo. The 60-year design life for the LMR presents a significant challenge to the development of database, extrapolation/prediction of long-term performance, and high temperature structural design methodology. The current Subsection NH is applicable to the design life only up to 34 years. No experimental data contain test durations of 525,000 hours, and it is impractical...

show abstract

The effect of environment on high-temperature hold time fatigue behavior of annealed 2.25 pct Cr 1 pct Mo steel

Cited by 20 publications

References 14 publications

Ratcheting‐fatigue behaviour of bainite 2.25Cr1MoV steel with tensile and compressed hold loading at 455°C

Ratcheting‐fatigue behaviour of bainite 2.25Cr1MoV steel with tensile and compressed hold loading at 455°C

Experimental and numerical characterization of low cycle fatigue and creep fatigue behaviour of P92 steel welded joint

Resolution of qualification issues for existing structural materials.

Contact Info

Product

Resources

About