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Creep–fatigue evaluation method for weld joints of Mod.9Cr–1Mo steel. Part I: Proposal of the evaluation method based on finite element analysis and uniaxial testing

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In this article, a method for evaluating the life cycle of a Mod.9Cr-1Mo steel weld joint based on finite element analysis (FEA) was proposed to predict the number of cycles to failure within a factor of 3.
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This article is published in Nuclear Engineering and Design.The article was published on 2017-11-01 and is currently open access. It has received 7 citations till now.

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Modelling creep-fatigue behaviours using a modified combined kinematic and isotropic hardening model considering the damage accumulation

TL;DR: In this paper, a modified combined kinematic and isotropic hardening model by introducing a nonlinear interaction damage accumulation constitutive model was proposed to capture the loop stress-strain behaviour until fracture and predict the failure life as the applied strain amplitudes and duration periods changed.
Journal ArticleDOI

Creep-fatigue evaluation method for weld joint of Mod.9Cr-1Mo steel Part II: Plate bending test and proposal of a simplified evaluation method

TL;DR: In this paper, a method for evaluating the creep-fatigue life of Mod.9Cr-1Mo steel weld joints was proposed based on finite element analysis (FEA) and a series of cyclic plate bending tests of longitudinal and horizontal seamed plates.
Journal ArticleDOI

Creep-fatigue interactions in type 316H under typical high-temperature power plant operating conditions

TL;DR: In this paper, a micromechanical crystal plasticity self-consistent model (SCM) was used to analyse loading histories in 316H stainless steel and the effect of cyclic plasticity on creep was quantified.
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Journal ArticleDOI

Creep damage evaluation of 9Cr–1Mo–V–Nb steel welded joints showing Type IV fracture

TL;DR: In this article, the authors conducted long-term creep rupture tests for 9Cr-1Mo-V-Nb (P91) steel welded joints and examined the relationship between microstructural changes and crack nucleation site and propagation path.
Journal ArticleDOI

Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor

TL;DR: In this paper, the progress of the design study and research and development (R&D) for the Japan Sodium-cooled Fast Reactor (JSFR) implemented in the “Fast Reactor Cycle Technology Development (FaCT)” project is described.
Proceedings ArticleDOI

Evaluation of Creep Strength Reduction Factors for Welded Joints of Modified 9Cr-1Mo Steel (P91)

Abstract: In order to review the allowable creep strength of high Cr ferritic steels, creep rupture data of base metal and welded joints have been collected and long-term creep strength have been analyzed in the SHC committee in Japan since 2004. In the present paper, the creep rupture data of 370 points for welded joint specimens of modified 9Cr-1Mo steel (ASME Grade 91) offered from seven Japanese companies and institutes were analyzed. These data clearly indicated that the creep strength of welded joints was lower than that of base metal due to Type IV fracture in HAZ at or above 600°C. From the activities of this committee, the master curve for life evaluation of welded joints of Gr.91 steel could be represented as follows: LMP==34154+3494(log σ)−2574(log σ)2, C=31.4 The reduction factor of 100,000 hours creep rupture strength of welded joint to base metal was concluded to be 0.75 at 600°C and 0.70 at 650°C for the Gr.91 steel.Copyright © 2006 by ASME
Journal ArticleDOI

Simplified analysis and design for elevated temperature components of Monju

TL;DR: The Japanese Prototype Fast Breeder Reactor Monju is now at a stage of submitting applications to the government for getting Construction Permission as discussed by the authors, and detailed structural design of components is now in progress.
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Q1. What contributions have the authors mentioned in the paper "Creep-fatigue evaluation method for weld joints of mod.9cr-1mo steel, 1; proposal of the evaluation method based on finite element analysis and uniaxial testing" ?

Title Creep-fatigue evaluation method for weld joints of Mod. 9Cr-1Mo steel, 1 ; Proposal of the evaluation method based on finite element analysis and uniaxial testing Author ( s ) Ando Masanori, Takaya Shigeru Citation Nuclear Engineering and Design, 323, p. 463-473 ( 2017 ) Text Version Author Accepted Manuscript URL https: //jopss. 

To adopt Mod.9Cr-1Mo steel, the individual failure mechanism (Type IV cracking) at the weld joints [6-8] should be considered in piping and component design. 

Because the creep-fatigue test is performed by controlling the strain, the strain amplitude between the gauge grips is held constant during the holding period. 

On the other hand, with respect to failure mechanism of SFRs components, the most important failure mode to be prevented in the design is creep-fatigue. 

The elastic follow-up method was originally developed in Japan, and a value of q = 3 was defined in the code as a conservative value [4] [5]. 

Because inelastic FEA using a model with welding lines in the components was not practical in the components design, a procedure based on elastic FEA is required. 

Since a failure mode that originated in the HAZ was also recognized through creep-fatigue testing and the available data research, the authors have investigated the evaluation method of creep-fatigue life for the weld joints of Mod.9Cr-1Mo steel considering the HAZ. 

Because the creep-fatigue test was performed by controlling the strain amplitude, the total strain amplitude in the gauge length generated by the tension loading of the model end was monitored for each historical step in the FEA. 

Under operating conditions with low primary stress, the equation for estimating the total strain range, εt, in the strain concentration region exhibiting elastic follow-up behavior in the JSME FRs13 / 36code is as follows:nt K ee e= , (3)where εn is the nominal strain range, and Kε is defined byeKKK ′=e , (4)wheremS3Sn > , and (5)( )( )nme SS311q1K −−+=′ . (6) In the equation (5) and (6), Sn is the nominal stress range, K is the stress concentration factor,and q = 3. 

To avoid the effect of boundary conditions on the stress-strain redistribution during creep relaxation, the entire specimen was modeled when simulating the creep-fatigue test. 

Without this strain feedback technique, strain amplitude within gauge length is changed by stress-strain redistribution due to creep behavior during the holding. 

The overestimation of failure cycles in Fig.15 is attributed to the fact that the estimated creep-fatigue test data were limited at 550 °C and the most of the data were obtained by the test11 / 36with 1.0 h or less holding, while there were each one data obtained with 3.0 h and 10.0 h holding. 

Using optical microscopy, the grain size number (ASTM E 112) in the BM and HAZ of the original weld joint were estimated to be 8.0 and 10 to 12, respectively.